TPX 

System Specification

TPX-RQMT-ASPEC Rev. 0, Draft C

SEPTEMBER 22, 1995

Prepared by: __________________________________
 D. Johnson, TPX SIS Responsible Engineer 

Reviewed by: __________________________________
W. Robinette,  TPX SIS Project Manager

Reviewed by: __________________________________
W. Reierson, TPX Deputy Project Engineer

Reviewed by: __________________________________
J. C. Sinnis, TPX Project Engineer

Reviewed by: __________________________________
G. H. Neilson, TPX Physics Head

Approved by: __________________________________
J. A. Schmidt, TPX Project Director

CONTROLLED DOCUMENT
This is a controlled document. To assure, prior to use, that this copy is current, check the TPX File Share Server.

The Original is on file at TPX.  
95-950922-TRW-DJohnson-01

Record of Revisions
Revision	Date	ECP	Description of Change	
Draft A	5/9/95 	-	Initial Draft	
Draft B	8/31/95	-	ECPs incorporated per  GRD Rev. 1
Document reorganized for compliance with MIL-STD-490A.
Missing GRD requirements incorporated.
Additional design constraints incorporated.
Section 3.1 expanded.
Sections 4, 5 and 6 added.
Incorporation of comments against Draft Rev. A. 	
DRAFT C	09/22/95	-	Reorganized section 3.2.1 to relocate chamber conditioning requirements under experimental operations.
Incorporated requirements for heating loads and for the heating and cooling system.
Minor changes for clarity and accuracy.	

Table of Contents
1.  SCOPE	1
1.1  Identification	1
1.2  System Overview	1
1.3  Document Overview	1
1.3.1  Relationship of System to Subsystem Requirements	1
1.3.2  Incomplete Requirements	1
1.3.3  Use of Drawings	2
2.  APPLICABLE DOCUMENTS	3
2.1  Government Documents	3
2.2  Non-Government Documents	3
3.  SYSTEM REQUIREMENTS	5
3.1  System Definition	5
3.1.1  General Description	5
3.1.2  System Elements	6
3.1.2.1  WBS 11 - Plasma Facing Components (PFC)	7
3.1.2.2  WBS 12 - Vacuum Vessel (VV) System	8
3.1.2.3  WBS 13 - Toroidal Field (TF) Magnet System	8
3.1.2.4  WBS 14 - Poloidal Field (PF) Magnet System	8
3.1.2.5  WBS 15 - Cryostat	8
3.1.2.6  WBS 16 - Tokamak Support Structure	8
3.1.2.7  WBS 17 - Tokamak Assembly	8
3.1.2.8  WBS 18 - Tokamak Shielding	8
3.1.2.9  WBS 19 - Field Error Correction (FEC) and Fast Plasma Position Control (FPPC) Coil Systems	8
3.1.2.10  WBS 21 - Neutral Beam Injection System	8
3.1.2.11  WBS 22 - Electron Cyclotron Heating and Current Drive	9
3.1.2.12  WBS 23 - Ion Cyclotron Heating and Fast Wave Current Drive	9
3.1.2.13  WBS 24 - Lower Hybrid Heating and Lower Hybrid Current Drive	9
3.1.2.14  WBS 31 - Fuel Storage and Delivery Systems	9
3.1.2.15  WBS 32 - Pellet Injection System	9
3.1.2.16  WBS 33 - Radiation Monitoring and Tritium Cleanup Systems	9
3.1.2.17  WBS 34 - Vacuum Pumping Systems	9
3.1.2.18  WBS 4 - Power Systems	9
3.1.2.19  WBS 5 - Maintenance Systems	10
3.1.2.20  WBS 61 - Central Instrumentation and Control (I&C) Systems	10
3.1.2.21  WBS 62 - Plasma Diagnostics	10
3.1.2.22  WBS 71 - Building, Modifications, and Site Improvements	10
3.1.2.23  WBS 72 - Cryogenic Systems	10
3.1.2.24  WBS 73 - Heating and Cooling Systems	10
3.1.2.25  WBS 74 - Test Cell Penetrations	10
3.1.3  System Functions	10
3.1.4  Reference Scenarios	13
3.1.4.1  HC Scenario	13
3.1.4.2  LC Scenario	13
3.1.4.3  Steady State Operation	13
3.1.5  Interface Definition	13
3.1.5.1  Commercial Power	13
3.1.5.2  Local Water	14
3.1.5.3  Data Processing and Remote I&C	14
3.1.5.4  Existing Facilities	14
3.2  Characteristics	15
3.2.1  Performance Characteristics	15
3.2.1.1  Facility Startup	15
3.2.1.2  Reserved	15
3.2.1.3  Pre-Operational Initialization and Checks	15
3.2.1.3.1  Pre-Operational Verification	15
3.2.1.3.2  Magnet Cooldown and Warmup	15
3.2.1.3.2.1  Magnet Cooldown Timelines	15
3.2.1.3.2.2  Magnet Warmup Timeline	16
3.2.1.3.2.3  Cooldown-Warmup Cycles	16
3.2.1.3.2.4  Coil Quenching	16
3.2.1.3.2.5  Cryostat Evacuation Prior to Cooldown	16
3.2.1.3.2.6  Use of MFTF-B Refrigerator	16
3.2.1.4  Experimental Operations	16
3.2.1.4.1  Plasma Chamber Conditioning	16
3.2.1.4.1.1  Base Pressure	16
3.2.1.4.1.1.1  Base Pressure Development	16
3.2.1.4.1.1.2  Impurity Gas Load During Pumpdown	16
3.2.1.4.1.2  Bakeout	17
3.2.1.4.1.2.1  Bakeout Temperatures	17
3.2.1.4.1.2.2  Bakeout Timelines	17
3.2.1.4.1.3  Glow Discharge Cleaning	17
3.2.1.4.1.3.1  GDC Gasses	17
3.2.1.4.1.3.2  Use of Hydrogen/Deuterium During GDC	17
3.2.1.4.1.3.3  GDC Between Shots	17
3.2.1.4.1.4  Boronization	17
3.2.1.4.1.5  Pre-Shot Temperature	18
3.2.1.4.2  Plasma Startup	18
3.2.1.4.2.1  Toroidal Resistance	18
3.2.1.4.2.2  Initiation of HC and LC Scenarios	18
3.2.1.4.2.3  HC and LC Scenario Startup Sequence	18
3.2.1.4.2.4  HC and LC Scenario Coil Currents	19
3.2.1.4.2.5  Startup Scenario Variants	19
3.2.1.4.3  Plasma Magnetic Field Requirements	19
3.2.1.4.3.1  Toroidal Field/Plasma Current Directionality	19
3.2.1.4.3.2  Toroidal Field Requirements	19
3.2.1.4.3.3  Poloidal Field Requirements	20
3.2.1.4.3.3.1  Reference Scenarios	20
3.2.1.4.3.3.1.1  PF Currents for HC and LC Scenarios	20
3.2.1.4.3.3.1.2  High Current, Double Null (HC) Scenario	20
3.2.1.4.3.3.1.3  Low Current, Double Null (LC) Scenario	20
3.2.1.4.3.3.2  Flexibility	21
3.2.1.4.3.3.2.1  Double Null Divertor Operation	21
3.2.1.4.3.3.2.1.1  Full Current Operation	21
3.2.1.4.3.3.2.1.2  q=5 Operation	21
3.2.1.4.3.3.2.2  Single Null Divertor Operation	22
3.2.1.4.3.3.3  Equilibrium Control	22
3.2.1.4.3.3.3.1  Radial Plasma Position Control	22
3.2.1.4.3.3.3.2  Vertical Plasma Position Control	23
3.2.1.4.3.3.3.3  Separatrix Position Control	23
3.2.1.4.3.3.3.4  External Kink Mode Control	24
3.2.1.4.3.4  Field Errors	24
3.2.1.4.3.4.1  System Field Error Requirements	24
3.2.1.4.3.4.2  FEC Coil Current Requirements	24
3.2.1.4.3.4.3  Field Error Requirement and FEC Coil Current Allocations	25
3.2.1.4.4  Power Handling	25
3.2.1.4.4.1  Scrape-off Layer (SOL) Envelopes	25
3.2.1.4.4.2  Maximum Heating Power	26
3.2.1.4.4.3  Power Partitioning	26
3.2.1.4.5  Disruption Handling	27
3.2.1.4.6  Plasma Heating and Current Drive	28
3.2.1.4.6.1  Heating and Current Drive Technologies	28
3.2.1.4.6.2  Flexibility of Current Density Control	28
3.2.1.4.7  Operational Requirements	28
3.2.1.4.7.1  Pulse Operation	28
3.2.1.4.7.2  Pulse Repetition Rate	28
3.2.1.5  Experiment Shutdown	28
3.2.1.5.1  Normal Shutdown	28
3.2.1.5.2  Abnormal Shutdown	28
3.2.1.6  Instrumentation, Control and Data Acquisition	29
3.2.1.7  Plasma Diagnostics	29
3.2.1.8  Facility Shutdown	30
3.2.1.9  Tokamak Fuel	30
3.2.1.9.1  Gas Injection	30
3.2.1.9.2  Pellet Injection	30
3.2.1.10  System Cooling	30
3.2.1.11  System Power	30
3.2.1.11.1  Allowable Voltage Variation	30
3.2.2  System Capability Relationships	30
3.2.3  External Interface Requirements	30
3.2.3.1  Commercial Power Interface	30
3.2.3.2  Local Water Interface	30
3.2.3.3  Data Processing and Remote I&C Interface	32
3.2.4  Physical Characteristics	32
3.2.4.1  System Configuration	32
3.2.5  System Quality Factors	32
3.2.5.1  Reliability	32
3.2.5.1.1  Mission Reliability	32
3.2.5.1.2  Shot Reliability	32
3.2.5.1.2.1  Subsystem Shot Reliability	32
3.2.5.2  Maintainability	32
3.2.5.2.1  Scheduled Maintenance	32
3.2.5.2.2  Remote Maintenance	32
3.2.5.2.3  Hands-on Maintenance	33
3.2.5.2.3.1  ICH/FWCD Hands-on Maintenance	33
3.2.5.2.4  TPX Assembly and Disassembly	34
3.2.5.2.5  Two Man Lift Limits	34
3.2.5.2.6  Failure of Fault Detection Equipment	34
3.2.5.2.7  Accessibility of Test Points	34
3.2.5.2.8  Access to Panels	34
3.2.5.2.9  Mean Down Time	34
3.2.5.2.10  Decontamination and Disposal	34
3.2.5.3  Availability	34
3.2.5.3.1  Subsystem Availability	34
3.2.5.4  Additional Quality Factors	35
3.2.5.4.1.1  Annual Operating Limits	35
3.2.5.4.1.2  Lifetime Operating Limits	36
3.2.6  Environmental Conditions	36
3.2.6.1  Natural Environments	36
3.2.6.1.1  Temperature (Drybulb)	36
3.2.6.1.2  Humidity	36
3.2.6.1.3  Fungus Growth	36
3.2.6.1.4  Sand and Dust	36
3.2.6.1.5  Wind	36
3.2.6.1.6  Lightning	37
3.2.6.1.7  Seismic	37
3.2.6.1.8  Solar Heating	37
3.2.6.1.9 Atmospheric Pressure	37
3.2.6.2  Induced Environments	38
3.2.6.2.1  Vibration	38
3.2.6.2.2  Shock	38
3.2.6.2.3  Neutron Source Rates/Yields	38
3.2.6.3  Abnormal Environments	38
3.2.6.3.1  Missile Impact	38
3.2.7  Transportability	38
3.2.8  Flexibility and Expansion	39
3.2.8.1  Accommodation of Future Startup Scenarios	39
3.2.8.2  Accommodation of  Vacuum Pumping Rate Upgrades	39
3.2.8.2.1  Neutral Pressure Vacuum Pumping Rate Upgrade	39
3.2.8.2.2  Maximum Pumping Rates Upgrade	40
3.2.8.2.3  Minimum Vacuum Pumping Speed Upgrade	40
3.2.8.3  Accommodation of Plasma Heating and Current Drive Upgrades	40
3.2.8.3.1  Electron Cyclotron Heating/Current Drive Upgrade	40
3.2.8.3.1.1  10 MW ECH/ECCD Power	40
3.2.8.3.1.2  ECH/ECCD Capabilities	40
3.2.8.3.2  Neutral Beam Power Upgrade to 24MW	40
3.2.8.3.3  ICH/FWCD Upgrades	40
3.2.8.3.3.1  ICH/FWCD Power Upgrade to 18 MW	40
3.2.8.3.3.2  ICH/FWCD Operating Frequency Upgrade	40
3.2.8.4  Upgrade to Steady State Operation	41
3.2.8.4.1  Steady State Operation	41
3.2.8.4.2  Steady State Neutral Beam Power	41
3.2.8.4.3  Steady State Cooling Capability	41
3.2.8.5  Upgrade for Tritium Operation	41
3.2.8.6  External Kink Mode Control Upgrade	41
3.2.8.7  Diagnostics Upgrades	41
3.2.9  Portability	41
3.3  Design and Construction	41
3.3.1  Materials, Processes, and Parts	41
3.3.1.1  Magnetic Permeability	41
3.3.1.2  Vacuum Boundary Materials	41
3.3.1.3  Structural and Cryogenic Criteria	43
3.3.1.4  Corrosion Prevention and Control	43
3.3.1.5  Neutral Beam Armor Materials	43
3.3.1.6  Divertor Materials	43
3.3.1.7  Limiter Materials	43
3.3.1.8  Activation	43
3.3.2  Electromagnetic Radiation (EMR)	43
3.3.2.1  Electrical Referencing Requirements	43
3.3.2.2  Electrical bonding	44
3.3.2.3.1  Equipment cases	44
3.3.2.3.2  Shield termination	45
3.3.2.3.3  Cable Shield Effectiveness	45
3.3.2.4  Electromagnetic Environment	45
3.3.2.5  EMI Characteristics	45
3.3.2.5.1  Conductors Exiting the Tokamak	45
3.3.2.5.2  Tokamak Ports Open to RF Heating Fields	45
3.3.2.5.3  Diagnostics Equipment RF Tight Enclosures, Racks, and Cabling	45
3.3.3  Nameplates and Product Marking	45
3.3.3.1  Labels	45
3.3.3.2  Identifying Devices	45
3.3.4  Workmanship	46
3.3.5  Interchangeability	46
3.3.6  Environmental, Safety, and Health (ES&H) Requirements	46
3.3.6.1  General Safety	46
3.3.6.2  Safety Hazards	46
3.3.6.2.1  Neutron and Gamma Shielding	46
3.3.6.2.2  Radiation Monitoring	46
3.3.6.2.3  Controlled Access System	46
3.3.6.2.4  Diborane Gas Exposure	46
3.3.6.3  Personnel Safety	46
3.3.6.4  Flammability	46
3.3.6.5  Fire Suppression	46
3.3.6.6  Hazardous Materials	47
3.3.6.6.1  Activated Air Emissions	47
3.3.6.6.2  Hazardous Liquid Containment	47
3.3.6.7  Electrical Safety	47
3.3.6.8  Radiological Design Objectives	47
3.3.7  Human Engineering	47
3.3.7.1  Anthropometry	47
3.3.7.2  Human Environments	47
3.3.7.2.1  Temperature and Humidity	47
3.3.7.2.2  Ventilation:	47
3.3.7.2.3  Lighting	47
3.3.7.2.4  Emergency Lighting	48
3.3.7.2.5  Noise	48
3.3.7.2.6  Vibration	48
3.3.7.3  Component Arrangement	49
3.3.7.4  Protective Equipment	49
3.3.7.5  Display Devices	49
3.3.7.6  System Controls	49
3.3.7.6.1  Operator Controls	49
3.3.7.6.2  Component Controls	49
3.3.7.7  Warning and Annunciator Systems	50
3.3.7.8  Communications Systems	50
3.3.8  Nuclear Control	50
3.3.9  System Security	50
3.3.10  Government Furnished Property Usage	51
3.3.11  Computer Resource Reserve Capacity	51
3.4  Documentation	51
3.5  Logistics	51
3.5.1  Maintenance	51
3.5.1.1  Test Cell Maintenance	51
3.5.1.1.1  Hands-on Maintenance	51
3.5.1.1.2  Remote Maintenance	51
3.5.2  Supply	51
3.5.3  Facilities	52
3.6  Personnel and Training	52
3.6.1  Personnel	52
3.6.2  Training	52
3.7  Characteristics of Subordinate Elements	52
3.7.1  Plasma Facing Components (PFC)	52
3.7.1.1  Resistive Breaks	52
3.7.1.2  Component Power Handling Requirements	52
3.7.1.2.1  Divertor Power Handling	52
3.7.1.2.2  Inner Toroidal Limiter Power Handling	52
3.7.1.2.3  Outer Toroidal Limiter Power Handling	52
3.7.1.2.4  Neutral Beam Armor Power Handling	52
3.7.1.2.5  Poloidal Limiters Power Handling	53
3.7.1.2.6  Other Line-of-Sight Components Power Handling	53
3.7.1.3  Divertor Configuration	53
3.7.1.3.1  Peak Heat Load Reduction	53
3.7.1.3.2  High Heat Flux Region Geometry	53
3.7.1.3.3  Maximum Auxiliary Baffle Leak Rate	53
3.7.1.3.4  Divertor Assembly Reconfiguration	53
3.7.1.4  Limiter Configuration	53
3.7.2  Vacuum Vessel (VV) System	54
3.7.2.1  Base Pressure	54
3.7.2.2  Leak Rate	54
3.7.2.3  Alignment and Operational Stability	54
3.7.2.4  Toroidal Resistance	54
3.7.3  Toroidal Field (TF) System	54
3.7.4  Poloidal Field (PF) System	55
3.7.5  Cryostat	55
3.7.6  Tokamak Support Structure	55
3.7.7  Tokamak Assembly	55
3.7.8  Tokamak Shielding	55
3.7.9  FEC and FPPC Coil Systems	55
3.7.9.1  FEC Coil System	55
3.7.9.2  FPPC Coil System	56
3.7.10  Neutral Beam System	56
3.7.10.1  8MW Neutral Beam Power	56
3.7.10.2  Beamline Orientation	56
3.7.11  Electron Cyclotron Heating and Current Drive	56
3.7.12  Ion Cyclotron Heating and Fast Wave Current Drive	56
3.7.12.1  6 MW ICH/FWCD Power	56
3.7.12.2  ICH/FWCD Power at a Single Frequency	56
3.7.12.3  ICH/FWCD Power at Three Frequencies	57
3.7.12.4  Use of Faraday Shield	57
3.7.13  Lower Hybrid Heating and Current Drive (LHH/LHCD)	57
3.7.13.1  3MW LHH/LHCD Power	57
3.7.13.2  Dynamic Variance of Wave Number Spectrum	57
3.7.13.3  Surface Configuration of LH Launcher	57
3.7.13.4  Movement of LH Launcher	57
3.7.14  Fuel Storage and Delivery Systems	57
3.7.15  Pellet Injection System	57
3.7.16  Radiation Monitoring and Tritium Cleanup Systems	58
3.7.17  Vacuum Pumping Systems	58
3.7.17.1  Vacuum Pumping Speed and Throughput	58
3.7.17.1.1  Neutral Pressure Vacuum Pumping Rates	58
3.7.17.1.2  Maximum Vacuum Pumping Rates	58
3.7.17.1.3  Minimum Vacuum Pumping Speeds	58
3.7.17.1.4  Vacuum Pumping Speed Control	58
3.7.18  Power Systems	58
3.7.19  Maintenance Systems	58
3.7.20  Central I&C Systems	58
3.7.21  Plasma Diagnostics	58
3.7.21.1  Plasma Control Diagnostics	58
3.7.21.2  Confinement Diagnostics	59
3.7.21.3  Divertor/Edge Plasma Diagnostics	59
3.7.21.4  Fusion Yield Diagnostics	59
3.7.21.5  Baseline Diagnostics	59
3.7.22  Building, Modifications, and Site Improvements	59
3.7.23  Cryogenic Systems	59
3.7.24  Water Systems	60
3.7.24.1 50°C Cooling Water System	60
3.7.24.2  Borated Water System	60
3.7.24.3  Bakeout System	60
3.7.24.4  Chilled Water System	61
3.7.24.5  Demineralized Cooling Water System	61
3.7.24.6  Heat Rejection System	61
3.7.24.7  Makeup Water System	61
3.7.24.8  Gas Blanket and Vent System	62
3.7.25  Test Cell Penetrations	63
3.8  Precedence	63
3.9  Qualification	63
3.10  Standard Sample	63
3.11  Preproduction Sample	63
4.  QUALITY ASSURANCE PROVISIONS	64
4.1  General	64
4.2  Responsibility For Inspection	64
4.3  Responsibility For Conformance	64
4.4  Inspection Verification Methods	64
4.5  Quality Conformance	65
4.5.1  Detailed Quality Conformance Requirements	65
4.5.1.1  Magnet Cooldown Timelines (ref. 3.2.1.3.2.1)	65
4.5.1.2  Magnet Warmup Timeline (ref.  3.2.1.3.2.2)	65
4.5.1.3  Cooldown-Warmup Cycles (ref.  3.2.1.3.2.3)	65
4.5.1.4  Remote Maintenance (ref. 3.2.5.2.2)	65
5.  PREPARATION FOR DELIVERY	73
6.  NOTES	74
6.1  Requirement References	74
6.2  Field Error Calculation	75
6.3  Definitions	76
6.4  Acronyms	78

LIST OF TABLES
Table 3.1.2 TPX Subsystems and WBS Identifiers	6
Table 3.1.5.2  TPX Local Water Interface	14
Table 3.2.1.4.3.3.2.1.1 Full Current Operation States	21
Table 3.2.1.4.3.3.2.1.2  q=5 States	21
Table 3.2.1.4.3.3.2.2  Single Null Divertor Operation States	22
Table 3.2.1.4.3.4.3  Field Error Allocations	25
Table 3.2.1.4.5 Disruption Characteristics	27
Table 3.2.1.10  Subsystem Heating Loads	31
Table 3.2.1.11  TPX System Power	31
Table 3.2.4.1  System Configuration Drawings	32
Table 3.2.5.1.2.1 Shot Reliability Allocations	33
Table 3.2.5.3.1 Operational Availability Allocations	35
Table 3.2.6.1.7  Performance Class Designations	38
Table 3.2.6.2.3  Neutron Source Rates/Yields for D and DT Operation	39
Table 3.2.8.4.3  Steady State Subsystem Heating Loads	42
Table 3.2.8.7  Diagnostics Upgrade Accommodations	42
Table 3.3.6.8  Radiological Design Objectives	48
Table 3.3.10 Government Furnished Equipment, Information, and Software	51
Table 3.7.1.2.6  Other line-of-Sight Components Power Handling	53
Table 3.7.21.5  Baseline Diagnostics	59
Table 3.7.24.1  50°C Cooling Water System Performance Requirements	60
Table 3.7.24.2  Borated Water System Performance Requirements	61
Table 3.7.24.4  Chilled Water System Performance Requirements	61
Table 3.7.24.5  Demineralized Cooling Water System Requirements	62
Table 3.7.24.6  Heat Rejection System Performance Requirements	62
Table 4.5 Quality Conformance Matrix	66
Table 6.3  General Design Guidelines for Potential Events	77

LIST OF FIGURES
Figure 1.3.1  Relationship of System Specification to Subsystem Development Specifications	2
Figure 3.1.1 TPX Coordinate System	5
Figure 3.1.2 TPX System Diagram	7
Figure 3.1.3-1  TPX System Master Flow (0.0)	11
Figure 3.1.3-2  TPX Experimental Operations Flow (1.0)	12
Figure 3.1.5 TPX External Interfaces	13
Figure 3.2.1.4.4.3-1 Power Partitioning for High Core Radiation Condition	26
Figure 3.2.1.4.4.3-2 Power Partitioning for Low Core Radiation Condition	27
Figure 3.2.6.1.6  Lightning Strike Current Model Waveform - 2 % Exceedence Level Model	37

APPENDICES

Appendix 10  - PF Coil Current Requirements

1.  SCOPE
1.1  Identification

This document, the Tokamak Physics Experiment (TPX) System Specification, specifies the performance, design, documentation, and quality assurance requirements for the TPX to be installed and operated at the Princeton Plasma Physics Laboratory (PPPL).

1.2  System Overview

The purpose of the TPX is to demonstrate long-pulse tokamak operation with high plasma pressure and enhanced confinement.  The specific mission of TPX is to develop the scientific basis for a compact and continuously operating tokamak fusion reactor.  The combined results of the International Thermonuclear Experimental Reactor (ITER) and TPX will lead to a more economical demonstration power reactor.

1.3  Document Overview

Requirements for TPX are derived from the TPX Project Definition Statement (PDS) and General Requirements Document (GRD).

The specification format is a system specification (Type A) per MIL-STD-490A.  It is developed in accordance with DI-CMAN-80008A dated February 29, 1988.  It is to be used as the basis for developing all lower level (subsystem and equipment) technical specifications for the TPX Project.

1.3.1  Relationship of System to Subsystem Requirements

The specification approach outlined within MIL-STD-490A provides for a clear distinction between system and subsystem requirements as well as between performance requirements and design constraints.

Performance requirements state what functions a system has to perform and how well that function has to be performed.  Design constraints, on the other hand, are a set of limiting or boundary requirements that must be adhered to while allocating requirements or designing the system.  They are drawn from externally imposed sources (e.g., statutory regulations, DOE Orders, and PPPL ES&H Directives) as well as from internally imposed sources as a result of prior decisions which limit subsequent design alternatives.  

Within a system specification, section 3.2.1 defines the performance requirements that apply to the system as a whole.  Section 3.7 defines the allocation of the system performance requirements to specific subsystems.  The remainder of section 3 of the specification is generally considered to consist of design constraints.  As a rule, design constraints are not allocated to subsystems within section 3.7, however, subsystem specific constraints may be interspersed with the system level design constraints if they are considered significant enough for inclusion within the system specification.  See Figure 1.3.1.

Within a “B” level development specification for a subsystem, the subsystem performance requirements contained in section 3.2.1 are generally drawn from the applicable subsystem allocations within section 3.7 of the system specification.  Additional performance requirements at the subsystem level may also be included for completeness.  Similar to the system specification, section 3.7 of the “B” specification will contain performance requirements allocated to specific components or configuration items of the subsystem.  Design constraints for the subsystem will consist of derived system level constraints and other applicable constraints.

1.3.2  Incomplete Requirements

Within this document, the term “to be determined” (TBD) applied to a missing or incomplete requirement infers that additional effort (analysis, trade studies, etc.) is required before the requirement can be completed. The term “to be revised” (TBR) infers that the requirement may be reviewed for appropriateness by the Project and changed during the course of the system development activity.

Figure 1.3.1  Relationship of System Specification to Subsystem Development Specifications

1.3.3  Use of Drawings

The current references to the TPX system configuration drawings within this document do not reflect what would be recommended for the final configuration of this specification.  Typically drawings, including interface control drawings, are not referenced within a specification as they are subject to change and it can be difficult to isolate which part of the drawing is applicable as a source of requirements.  At the system level, the primary area where system level drawings can facilitate the statement of requirements is space allocation.  System level drawings which are used only to allocate space allocations or designate "keep out" zones may be appropriate as they tend to be more stable and are a convenient method to specify complex envelopes.  Drawings used for this purpose are referenced within the specification, but the drawings should be clearly annotated to distinguish between requirements and design detail provided for improved understanding.  The use of drawings to indicate how one subsystem may have to provide space or other support for another is not recommended.  In this case, the specific support requirements should be captured within the system specification with the details of the accommodation handled via interface control drawings.

2.  APPLICABLE DOCUMENTS
2.1  Government Documents

The following documents of the exact issue shown form a part of this specification to the extent specified herein.  In the event of conflict between the documents referenced herein and the contents of this specification, the contents of this specification shall be considered a superseding requirement.

In particular, TPX will be designed and operated in accordance with all applicable Department of Energy (DOE) Orders and PPPL Environment, Safety and Health Directives (ES&HDs).  In the event of conflicts between DOE Orders and PPPL ES&HDs, DOE Orders shall take precedence.

STANDARDS AND REGULATIONS

10CFR61
	Code of Federal Regulations, Title10, Class A low level waste limits	
29CFR1910	Code of Federal Regulations, Title29, 
	
DOE 5480.20
6/19/91	Personnel Selection, Qualification, Training, and Staffing Requirements at DOE Reactor and Non-Reactor Facilities
	
DOE 5480.7
11/16/87	Fire Protection

DOE 6430.1A	
4/6/89	General Design Criteria

MIL-STD-1367
10/2/89	Packaging, Handling, Storage, and Transportability Program Requirements for Systems and Equipments
	
MIL-STD-1472C
3/20/91
	Human Engineering Design Criteria for Military Systems, Equipment and Facilities
	
MIL-STD-810
7/14/89
	Environmental Test Methods and Engineering Guidelines
	
NUREG 0700	Guidelines for Control Room Design
	
NUREG CR-2496	Human Engineering Design Considerations for Cathode Ray Tube Generated Displays	

OTHER DOCUMENTS

	N/A

2.2  Non-Government Documents

The following documents of the exact issue shown form a part of this specification to the extent specified herein.  In the event of conflict between the documents referenced herein and the contents of this specification, the contents of this specification shall be considered a superseding requirement.

STANDARDS AND REGULATIONS

EPRI NP-3659	Human Factors Guide for Nuclear Power Plant Control Room
	
NFPA 101	Life Safety Code
	
PPPL ESHD 5008
6/93
	Environmental Safety and Health Manual, Princeton Plasma Physics Laboratory	
TPX-STND-001
1/17/95
	TPX Structural and Cryogenic Design Criteria
	
UCRL 15673	Human Factors Design Guidelines for Maintainability of DOE Nuclear Facilities, Lawrence Livermore National Laboratory
	
UCRL-15910
6/90	Design and Evaluation Guidelines for Department of Energy Facilities Subjected to Natural Phenomena Hazards, Lawrence Livermore National Laboratory	

OTHER DOCUMENTS

72-950328-LLNL-BFelker-01
3/28/95	MFTF-B Refrigerator Analysis Report

TPX Drawing E-13001	
	
TPX Drawing E-14002	
	
TPX Drawing E-14003	
	
TPX Drawing E-9413102	
	
TPX Drawing E-9413103	

3.  SYSTEM REQUIREMENTS
3.1  System Definition

3.1.1  General Description

TPX is a medium-scale (R=2.25m), high aspect ratio (A=4.5) tokamak with a toroidal field of 4T and a plasma current of 2MA.  The TPX facility will be sited at D-Site at PPPL.  The tokamak will be situated in the existing Tokamak Fusion Test Reactor (TFTR) test cell.

Figure 3.1.1 illustrates the right-handed coordinate system used for the tokamak and test cell on TPX.  The Z axis of the coordinate system is vertical and passes through the center of the pedestal at the 102' elevation in the TFTR test cell.  The major axis of the tokamak is coincident with the Z axis.  The origin of the coordinate system is at the 100' elevation, the floor of the TFTR test cell.  A monument on the floor will precisely locate the 100' level.  The Y axis is perpendicular to the North wall of the TFTR test cell.

The center of Bay A is located +13.5º (in the counter-clockwise direction) from the Y axis.  Toroidal angles (f) will be measured from the center of Bay A with counter-clockwise as the positive direction.

Figure 3.1.1 TPX Coordinate System
3.1.2  System Elements

New equipment and facilities required for TPX have been grouped in subsystems and identified in the TPX Project Work Breakdown Structure (WBS) as shown in Table 3.1.2.  There is other work required to execute the Project identified in the TPX Project WBS which is not related to new equipment and facilities and not shown in Table 3.1.2, such as project management, tokamak construction management, systems engineering, project physics, and preparation for operation.

Each of the TPX subsystems provides one or more functions which are essential to the successful operation of TPX.  The primary functions and subsystem interactions are illustrated in the system diagram provided in Figure 3.1.2. Note that there are functions and system interactions of lesser significance which are not show in the system diagram.

Table 3.1.2 TPX Subsystems and WBS Identifiers

WBS Identifier	
Subsystem	
11	Plasma Facing Components (PFC)	
12	Vacuum Vessel (VV) System 	
13	Toroidal Field (TF) Magnet System	
14	Poloidal Field (PF) Magnet System	
15	Cryostat	
16	Tokamak Support Structure	
17	Tokamak Assembly	
18	Tokamak Shielding	
19	Field Error Correction (FEC) and Fast Plasma Position Control (FPPC) Coil Systems	
21	Neutral Beam Injection System	
22	Electron Cyclotron Heating and Current Drive	
23	Ion Cyclotron Heating and Fast Wave Current Drive	
24	Lower Hybrid Heating and Lower Hybrid Current Drive	
31	Fuel Storage and Delivery System	
32	Pellet Injection System	
33	Radiation Monitoring and Tritium Cleanup System	
34	Vacuum Pumping Systems	
4	Power Systems	
5	Maintenance Systems	
61	Central Instrumentation and Control (I&C) Systems	
62	Plasma Diagnostics	
71	Building, Modifications, and Site Improvements	
72	Cryogenic Systems	
73	Heating and Cooling Systems	
74	Test Cell Penetrations	

Figure 3.1.2 TPX System Diagram

3.1.2.1  WBS 11 - Plasma Facing Components (PFC)

The plasma facing components include all the systems and related elements that serve to protect the vacuum vessel from the charged particle and radiation flux from the plasma and provide passive stabilization of the plasma.  These components include the remotely handled divertor, limiters (inboard, outboard and poloidal), armor (ripple armor, neutral beam armor and line of sight thermal shields), passive plates, and local I&C.

3.1.2.2  WBS 12 - Vacuum Vessel (VV) System 

The vacuum vessel system consists of the toroidal vessel inner and outer shells, stiffener rings, heating and cooling piping and passages between the shells, all ports and vacuum boundary closures, vessel supports, and leak control lines.  The vacuum vessel provides a vacuum boundary around the plasma chamber suitable for high vacuum conditions; structural support for all internal hardware; cooled substructure; access and support for vacuum pumping, plasma heating and diagnostics.  The vacuum vessel is designed to accommodate bakeout of the vessel and all internal components and provides for radiation shielding.  The vacuum vessel system also includes provisions for remote maintenance of the upper vertical ports. The vessel heating and cooling supply is provided by WBS 73, Heating and Cooling Systems.

3.1.2.3  WBS 13 - Toroidal Field (TF) Magnet System

The toroidal field (TF) magnets produce the toroidal magnetic field within the TPX device.  Includes the superconducting TF magnets, local I&C, and the TF bus and leads.

3.1.2.4  WBS 14 - Poloidal Field (PF) Magnet System

The poloidal field (PF) magnets produce the poloidal magnetic field within the TPX device.  Includes the superconducting PF magnets, local I&C, and the PF bus and leads.

3.1.2.5  WBS 15 - Cryostat

The cryostat encloses the TPX device to provide a suitable vacuum environment for the superconducting magnets which TPX utilizes.  This vacuum environment is required to create a thermal barrier between the ambient temperature test cell, and the liquid helium-cooled magnets.  Includes the cryostat structure, the wall insulation for the cryostat structure, attachments for the structural support of internal components, and the required electrical and mechanical penetrations.

3.1.2.6  WBS 16 - Tokamak Support Structure

The tokamak support structure provides the overall supporting mechanism for the tokamak components to the test cell floor.

3.1.2.7  WBS 17 - Tokamak Assembly

Tokamak assembly and integrated systems testing is responsible for developing the procedures, hardware, tooling, equipment and services to assemble and install the tokamak components in the test cell and to conduct pre-operational tests culminating in first plasma.

3.1.2.8  WBS 18 - Tokamak Shielding

The tokamak shielding provides radiation shielding that is integral to the vacuum vessel to protect materials, operating and maintenance personnel, and the general public.

3.1.2.9  WBS 19 - Field Error Correction (FEC) and Fast Plasma Position Control (FPPC) Coil Systems

The FEC and FPPC systems includes both the fast plasma position control coils and the field error correction control coils.  Includes the coils, coil joints, support structures, and electrical lines and coolant passages to both the power terminals and external coolant feed connections.

3.1.2.10  WBS 21 - Neutral Beam Injection System

The neutral beam injection (NBI) system provides positive-ion neutral beams for heating the plasma and for current drive.  Includes necessary modifications to the existing TFTR neutral beams, ion sources, cryogenic panels, power and cooling systems, local I&C, and any special remote maintenance tooling to maintain the neutral beam components.

3.1.2.11  WBS 22 - Electron Cyclotron Heating and Current Drive

The electron cyclotron heating (ECH) and electron cyclotron current drive (ECCD) is not currently part of the baseline TPX Project.  The current scope is limited to reserving the necessary equipment and port allocations to permit addition of ECH at a later date.  If added as an upgrade, the ECH may be used for start-up control and for current and pressure profile during operation.  Includes 120 GHz kylstrons (from General Atomics (GA)) and the supporting hardware.

3.1.2.12  WBS 23 - Ion Cyclotron Heating and Fast Wave Current Drive

The ion cyclotron heating (ICH) and fast wave current drive (FWCD) provides radio frequency (RF) waves for heating the plasma and current and pressure profile control.  Includes ICH power conversion equipment, ICH RF power generation equipment, ICH RF power transmission lines, tuning and matching system, launchers, the local I&C system, and any special remote maintenance tooling required to remotely maintain the ICH equipment.

3.1.2.13  WBS 24 - Lower Hybrid Heating and Lower Hybrid Current Drive

The lower hybrid heating (LHH) and lower hybrid current drive (LHCD) provides RF waves for current drive and current profile control.  Includes LH power conversion equipment, LH power generation equipment, LH power transmission lines, launchers, the local I&C system, and any special remote maintenance tooling required to remotely maintain the LH equipment.

3.1.2.14  WBS 31 - Fuel Storage and Delivery Systems

The fuel storage and delivery systems provide for the storage and injection into the torus of the hydrogen, deuterium, argon, or neon and diborane gases required for the operation of TPX.  Includes the necessary modification of the existing TFTR gas storage and delivery systems and the local I&C.

3.1.2.15  WBS 32 - Pellet Injection System

The pellet injection system is not currently part of the baseline TPX Project.  The current scope is limited to reserving the necessary equipment and port allocations to permit addition of the pellet injection system at a later date.  If added as an upgrade, the pellet injector will be used to provide high density fueling of TPX.

3.1.2.16  WBS 33 - Radiation Monitoring and Tritium Cleanup Systems

The radiation monitoring and tritium cleanup systems provide the necessary radiation monitoring capability and permit the safe handling and disposal of tritium waste.  Includes modifications to the existing TFTR systems and local I&C.

3.1.2.17  WBS 34 - Vacuum Pumping Systems

The vacuum pumping systems include new equipment (or modifications to existing TFTR equipment) for the following applications: torus ultrahigh vacuum pumping, forepumping, rough pumping, and glow discharge pumping; divertor pumping; vacuum system seal differential pumping and leak detection; rough pumping and foreline pumping for diagnostic, RF, and pellet fueling systems; cryostat vacuum pumping; vacuum systems instrumentation and control.

3.1.2.18  WBS 4 - Power Systems

The Power Systems include all the systems and related elements that provide conditioned electrical power and energy to the TPX systems. Includes the AC power, TF power, PF power, FPPC power, FEC power, and all other power systems activities. Also includes all equipment for instrumentation and local control.

3.1.2.19  WBS 5 - Maintenance Systems

The maintenance systems include integration and review of all the systems and related elements that provide a remote maintenance capability for in-vessel TPX components. Includes the basic remote handling equipment to maintain the tokamak systems, including transporters, power arm manipulators, dexterous arm manipulators, and general purpose tools. Includes a port transfer system, including the motive power required to drive the special tools, on the transporters that the special tools (developed by the individual subsystems) can use. Includes the hot cell, its equipment and general purpose tools, and for the viewing and lighting systems that are required to support remote handling operations.

3.1.2.20  WBS 61 - Central Instrumentation and Control (I&C) Systems

The central I&C systems provide the central supervisory control and data handling systems for TPX.  These systems interface with the subsystem local I&C systems and allow for control and monitoring of TPX experiments from the control room (local or remote) and the analysis of the results.

3.1.2.21  WBS 62 - Plasma Diagnostics

The plasma diagnostics provide the capability to measure the performance of the TPX device.  Design of the diagnostic elements near the torus includes consideration of space utilization, remote maintenance, neutron shielding, and allowable neutron lifetime dose levels.

3.1.2.22  WBS 71 - Building, Modifications, and Site Improvements

The building modifications and site improvements consists of the necessary modifications to existing TFTR and PPPL buildings and building utilities.  Includes new buildings for Liquid Helium (LHe) refrigeration and water systems pumps, preparation of yards for cryogenic and water storage tanks, test cell crane upgrade, and miscellaneous site improvements.

3.1.2.23  WBS 72 - Cryogenic Systems

The cryogenic system for TPX will provide all the refrigeration needed to cool the coils to a superconducting state.  It will provide the refrigeration by using supercritical helium and liquid nitrogen to various items and locations.

3.1.2.24  WBS 73 - Heating and Cooling Systems

The heating and cooling systems provide the steam, hot water, borated water, or cooled water required for bakeout and normal operation of TPX and all of its ancillary systems. The baseline system utilizes chilled water storage to provide cooling for the 1000 second pulses and rejects the heat to existing D- and C-Site cooling towers which together are capable of providing 50MW of continuous cooling.  Heated water and/or steam is provided by new electrical boilers.

3.1.2.25  WBS 74 - Test Cell Penetrations

The test cell penetrations consists of fire sealing of all penetrations into the test cell.

3.1.3  System Functions

The top-level system functions for TPX are detailed in Figure 3.1.3-1.  The function "1.0 Perform TPX Operations" was expanded and is provided as Figure 3.1.3-2.  This functional flow provides the foundation for the scope of the requirements within section 3.2.1 of this specification.

Figure 3.1.3-1  TPX System Master Flow (0.0)

Figure 3.1.3-2  TPX Experimental Operations Flow (1.0)

3.1.4  Reference Scenarios

The initial operation of the TPX will be per the high current (HC) and low current (LC) reference scenarios as described below.  To permit steady state operation, upgrades are required to the system's power supplies, cryogenic system, and other components outside the cryostat.

3.1.4.1  HC Scenario

The HC scenario is characterized by inductively ramping the plasma current to a full current of 2MA, applying auxiliary heating to raise the beta from its ohmic value to the Troyon limit (bN=3.5%), maintaining the plasma at full current and full beta, and then ramping the plasma current and beta down simultaneously. [GRD §1.1.1]

3.1.4.2  LC Scenario

The LC scenario is characterized by inductively ramping the plasma current to a full current of 0.4MA, applying auxiliary heating to raise the beta from its ohmic value to full beta at 0.4MA, linearly ramping the plasma current and beta to the EOB condition prescribed in the HC scenario, and then ramping the plasma current and beta down simultaneously. [GRD §1.1.2]

3.1.4.3  Steady State Operation

Steady state operation extends the duration of the plasma flattop for up to 100,000 seconds and incorporates the flexibility to operate at different points in b-li space.  The plasma current drive, in the HC and LC scenarios is a PF Magnet System function, but in steady state, it would be a function of the auxiliary heating system (non-inductive current drive).  Any combination of PF coil currents appearing between start-of-flattop (SOF) and end-of-beta (EOB) for the HC and LC scenarios can be run in steady state operation.

3.1.5  Interface Definition

The system will interface with the following external systems shown in Figure 3.1.5:

Figure 3.1.5 TPX External Interfaces

3.1.5.1  Commercial Power

TPX will utilize the electrical utility service provided to the PPPL site.  This service is provided via a 138 kV transmission line thermally rated at 600 Amp steady state (equivalent to roughly 140 MVA).  

3.1.5.2  Local Water

TPX will interface with the local water supply as described in Table 3.1.5.2 to support the water needs of the system (TBR).

Table 3.1.5.2  TPX Local Water Interface

Temperature (ºC)	Flow Rate (gpm)	Pressure (psi)	Volume (gal)	
TBD	TBD	TBD	TBD	

				

3.1.5.3  Data Processing and Remote I&C

TPX will receive commands and data from Remote I&C locations to control experimental operations and perform data processing (TBR).

3.1.5.4  Existing Facilities

The TPX system will interface to existing facilities for mounting, support, and shelter (TBR).

3.2  Characteristics

3.2.1  Performance Characteristics

3.2.1.1  Facility Startup

Description

Facility startup involves the startup of TPX equipment that is not part of the plasma startup for performing the experimental operations for a shot.  This includes startup of infrastructure subsystems like power, water, and environmental control systems (ECS) and other subsystems like diagnostics and I&C.  Facility startup also includes the monitoring of facility equipment operation.

Requirements

The TPX system shall provide the capability to perform a controlled startup of the facility, and verify that the facility equipment is functioning correctly. (TBR)

3.2.1.2  Reserved

3.2.1.3  Pre-Operational Initialization and Checks

Description:

Pre-operational initialization and checks involves the verification that diagnostics, I&C and all other appropriate operational equipment are calibrated and operating properly prior to initiating experimental operations. (TBR)

3.2.1.3.1  Pre-Operational Verification

Prior to the initiation of experimental operations, the system shall verify the proper functioning of the system. (TBR)

3.2.1.3.2  Magnet Cooldown and Warmup

Description.

Prior to experimental operations, the superconducting magnets must be cooled down from room temperature to operating temperature.  In order to avoid convective heat transfer to the superconducting magnets, the magnets are kept in a vacuum environment which is provided by the cryostat which surrounds the magnets.  In order to gain access to the cryostat, the magnets must be warmed up from operating temperature to room temperature.  

In the event of a magnet quench, parts of the magnet may be warmed to temperatures well in excess of the operating temperature.  It is necessary that a quenched magnet be capable of being cooled down to allow experimental operations to resume within a reasonable period of time.

3.2.1.3.2.1  Magnet Cooldown Timelines

	a)  Superconducting magnet systems shall be capable of being cooled down from room temperature to operating temperature within 240 hours using the refrigeration capacity of the existing Mirror Fusion Test Facility (MFTF-B) specified in 3.2.1.3.2.6.  For magnet cooldown and warmup, room temperature is defined as 20 +/- TBD ºC and operating temperature as TBDºC.  [2]

	b) All superconducting coils shall be capable of being cooled down to operating temperature following a coil quench within 12 (TBR) hours using the refrigeration capacity of the existing MFTF-B specified in 3.2.1.3.2.6. [3][4]

3.2.1.3.2.2  Magnet Warmup Timeline

Superconducting magnet systems shall be capable of being warmed up from operating temperature to room temperature within 120 hours using the existing heating capacity of the system specified in TBD.  Current flow within the conductor may be considered as a means to control the warmup operation.  [2]

3.2.1.3.2.3  Cooldown-Warmup Cycles

The design of the superconducting magnets shall allow for up to 100 (TBR)  cooldown-warmup cycles between room temperature and operating temperature.

3.2.1.3.2.4  Coil Quenching

Each superconducting coil shall be designed to withstand 50 quenches which is the maximum number of quenches expected for the worst case superconducting coil.

3.2.1.3.2.5  Cryostat Evacuation Prior to Cooldown

Prior to cooldown, the cryostat shall be evacuated to a base pressure of less than 10-5 torr.  The cryostat pressure shall be maintained at less than 10-5 torr when the superconducting magnets are below ambient temperature.

3.2.1.3.2.6  Use of MFTF-B Refrigerator

The existing MFTF-B refrigerator shall initially provide the helium refrigeration for the superconducting magnet systems.  Performance characteristics of the MFTF-B refrigerator are specified in the MFTF-B Refrigerator Analysis Report.

3.2.1.4  Experimental Operations

3.2.1.4.1  Plasma Chamber Conditioning

Description.

TPX requires high vacuum quality for good plasma performance.  In order to achieve high vacuum quality, the plasma chamber must be capable of being baked out at temperatures higher than normal operating temperatures.  The capability to perform glow discharge cleaning is also required.  Specific requirements for vacuum quality, bakeout, and glow discharge cleaning (GDC) are provided in the following sections

3.2.1.4.1.1  Base Pressure 

3.2.1.4.1.1.1  Base Pressure Development

The device and facility shall produce high vacuum conditions with a base partial pressure of less than or equal to 1x10-7 torr for fuel gases (Z less than or equal to 2) and a base partial pressure of less than or equal to 1x10-9 torr for impurity gases (Z greater than 2) at 65ºC. [GRD §1.9.1]  

3.2.1.4.1.1.2  Impurity Gas Load During Pumpdown

The impurity gas load during pumpdown to and at base pressure shall not exceed 1x10-5 torr-l/s. [GRD §1.9.1]

3.2.1.4.1.2  Bakeout

Description.  

The temperature of the vacuum vessel shell will be elevated to the nominal bakeout temperature of 350ºC by circulating high temperature, dry steam in the space between the two walls of the double-wall vacuum vessel and in the shield plugs located in the large horizontal ports.  Components internal to the vacuum vessel will be heated primarily by radiation and conduction from the vacuum vessel shell and shield plugs.

3.2.1.4.1.2.1  Bakeout Temperatures

	a)  During bakeout, the temperature of the vacuum vessel shell and all components internal to the vacuum vessel shall be maintained within ±25ºC of the nominal 350ºC bakeout temperature. [GRD §1.9.2]

	b) Vacuum pumping ducts and large horizontal ports shall have nominal bakeout temperatures of 350±TBDºC at the interface to the vacuum vessel and 150±TBDºC at the interface to the torus vacuum isolation valve. [GRD §1.9.2]

3.2.1.4.1.2.2  Bakeout Timelines

	a)  The vacuum vessel shell and all components internal to the vacuum vessel shall be capable of being raised to the bakeout temperatures within 30 hours and maintained at that temperature indefinitely. [6]

	b) Following bakeout, the vacuum vessel shell and all components internal to the vacuum vessel shall be capable of being returned to their pre-shot operating temperatures within 30 hours. [6]

	c) Although it is not necessary to keep the superconducting magnets at their operating temperature during bakeout, the superconducting magnets shall be capable of being returned to their pre-shot operating temperatures within the 30 hours following completion of bakeout.

3.2.1.4.1.3  Glow Discharge Cleaning

The device shall provide a glow discharge cleaning (GDC) capability with DC glow in 10-20 mtorr at 400 V and 20 A for periods up to 14 days with the vacuum vessel at nominal bakeout temperature of 350±25 ºC and a throughput 44 torr-l/s (He).  [GRD §1.9.3]

3.2.1.4.1.3.1  GDC Gasses

The device shall be capable of using any of the following gases for GDC:  hydrogen, deuterium, helium, and diborane. [GRD §1.9.3 as amplified per PDD §8.6.3]

3.2.1.4.1.3.2  Use of Hydrogen/Deuterium During GDC

The cumulative time over the life of TPX during which GDC is performed with hydrogen or deuterium shall be administratively controlled to be less than TBD days in order to guard against hydrogen embrittlement of components which might be susceptible to that phenomenon.

3.2.1.4.1.3.3  GDC Between Shots

The device shall provide the capability to perform GDC between shots with the vacuum vessel at the nominal pre-shot operating temperature. [GRD §1.9.3]

3.2.1.4.1.4  Boronization

The device shall provide the capability for boronization for all surfaces with line-of-sight to the plasma by the glow discharge technique specified in Section 3.2.1.4.1.3 using diborane gas. [GRD §1.9.4]

3.2.1.4.1.5  Pre-Shot Temperature

Interior vacuum vessel surfaces and all in-vessel components shall be maintained at a nominal pre-shot temperature of 65±5ºC between discharges.  Windows, feedthroughs, and similar components that are far from the plasma or that constitute a small fraction of the interior surface will be treated on an individual basis. [GRD §1.9.5]

3.2.1.4.2  Plasma Startup

3.2.1.4.2.1  Toroidal Resistance

The conducting structure shall include resistive breaks to provide sufficient toroidal resistance for penetration of the startup voltage. [GRD §1.8.4]

3.2.1.4.2.2  Initiation of HC and LC Scenarios

In order to promote reliable plasma initiation and operational flexibility, the HC and LC scenarios shall be initiated in an identical fashion, with a loop voltage of at least 12V.  

3.2.1.4.2.3  HC and LC Scenario Startup Sequence

The device and facility shall  be capable of inductively initiating the reference HC and LC discharge scenarios with a common, preprogrammed startup sequence meeting the specifications in the following subparagraphs.

	a)  The applied loop voltage shall rise to at least 12V in the absence of plasma.

	b)  Breakdown occurs when the loop voltage reaches 12V.  For a 7ms avalanche period ending at the time of breakdown, a field null with the following specifications shall be maintained:

1.	|Bp| less than or equal to 1mT within a 0.3m radius circle centered at R=2.47m, Z=0.0m.
2.	Loop voltage greater than or equal to 90% of the breakdown voltage.
3.	No other poloidal field nulls inside the vacuum vessel.
4.	Robust to 0.5% independent perturbations of all coil currents.

	c)  Starting from the time of breakdown, the plasma current shall increase to 100kA within 0.1s under the following assumptions:

1.	The plasma’s resistive voltage rises instantaneously at the time of breakdown to the breakdown voltage and then decays toward an asymptotic level greater than or equal to 1V.
2.	The plasma inductance is that of a circular torus centered at the breakdown null point and extending to the nearest limiter.

	d)  As the plasma current rises, the magnetic fields shall evolve to maintain the plasma in radial equilibrium near the midplane at a major radius between 2.0 and 2.47 m, under the assumption that bp+li/2=1.0. 

	e)  Starting from 30ms after the time of breakdown, the field index [defined as ‑(R/BZ)(dBZ/dR)] at the plasma position shall be maintained in the range +0.2 to +1.0 to provide positional stability.

	f)  Feedback control of the plasma current and radial equilibrium shall be established when the plasma current reaches 100 kA.

3.2.1.4.2.4  HC and LC Scenario Coil Currents

The PF and IC coil currents appropriate for the plasma startup described in 3.2.1.4.2.3 shall be as listed in Tables 10.1-14 and 10.1-15 for the HC and LC scenarios respectively.

3.2.1.4.2.5  Startup Scenario Variants

The device and facility shall provide startup flexibility such that the following variants on the scenario described in 3.2.1.4.2.3 are obtainable:

	a)  The field null position is centered at R=2.25m, Z=0.0m.  PF and IC coil currents appropriate for an inboard plasma startup are provided in Table 10.1-17.

	b)  A bias in the range of ±5mT in both the vertical and radial fields is applied throughout the avalanche period to compensate for stray fields.  PF and IC coil currents appropriate for vertical and radial field biases are provided in Tables 10.1-18 and 10.1-19 respectively.

	c)  The breakdown voltage is reduced to 3V, the avalanche period is 10ms, and the rise time to 100kA is 0.4s.  PF and IC coil currents appropriate for a 3V voltage breakdown are provided in Table 10.1-20.

3.2.1.4.3  Plasma Magnetic Field Requirements

3.2.1.4.3.1  Toroidal Field/Plasma Current Directionality

Description.

The coordinate system used on TPX is defined in Section 3.1.  A positive plasma current is in the positive f-direction (counter-clockwise direction) and provides a positive vertical field in the Z-direction.  A positive TF current (in the TF inner leg) is in the Z-direction and provides a positive toroidal field in the f-direction (counter-clockwise direction).  Positive radial fields and currents are in the R-direction, radially outward from the Z-axis, the major axis of the tokamak.

Performance Requirements.

	a) The tokamak shall be initially configured to drive plasma current in the positive direction with a negative toroidal field. [GRD §1.2.3]

	b) Plasma facing components and RF launchers shall be designed for two quadrant operation, i.e. the toroidal field will be bi-directional and the plasma current will always be in the opposite direction as the toroidal field. [GRD §1.2.3]

	c) All other equipment shall be designed for four quadrant operation, i.e. the toroidal field will be bi-directional and plasma current in the same direction and in the opposite direction as the toroidal field will be accommodated. [GRD §1.2.3]

3.2.1.4.3.2  Toroidal Field Requirements

	a) The device shall be designed to provide a toroidal field of 4T at a major radius of 2.25m for plasma startup (3.2.1.4.2), the reference scenarios (3.2.1.4.3.3.1); and equilibrium flexibility (3.2.1.4.1.3.2), while subject to the dynamic fields associated with equilibrium control (3.2.1.4.3.3.3) and plasma disruption (3.2.1.4.5) without quenching.  

The design shall satisfy the superconducting design criteria specified in the TPX Structural and Cryogenic Design Criteria for these operating conditions.

	b) The toroidal field will be held constant between plasma initiation and discharge termination.

	c) The toroidal field shall be capable of being ramped from full field (4T) to zero within 10 minutes and from zero to full field within 10 minutes in order to permit GDC between pulses. [GRD §1.9.3]
[GRD §1.9.5]

	d) The design shall allow for up to 6,000 charge-discharge cycles of the toroidal field coils (which includes cycling required for GDC). [GRD §2.4]

	e) The peak-to-average TF ripple shall be less than 0.4% over the plasma cross section. [GRD §1.6]

3.2.1.4.3.3  Poloidal Field Requirements

Description.  

PF coil current requirements have been determined on the basis of the PF coil envelopes and coil centers (at operating temperature) listed in Table 10.1-1. The PF coil currents listed in Appendix 10.1 satisfy plasma poloidal field requirements in the presence of the poloidal fields due to the TF coils and bus.  The PF coil currents required to compensate for the poloidal fields due to the TF coils and bus are listed in Table 10.1-1 for a TF coil current of 33.5kA which corresponds to a toroidal field of -4T at a major radius of 2.25m.

Performance Requirement.  

Nominal PF coil centers shall be within TBD of the coil centers listed in Table 10.1-1.

3.2.1.4.3.3.1  Reference Scenarios

The tokamak, ancillary systems, and facilities shall be shall be designed to satisfy the requirements attendant with the following scenarios:

a)	a high current, double null divertor (HC) scenario 
b)	a low current, double null divertor (LC) scenario

3.2.1.4.3.3.1.1  PF Currents for HC and LC Scenarios

The PF coil and PF coil power systems shall be designed such that any combination of PF coil currents appearing between start of flattop (SOF) state and end of beta (EOB) state for the HC and LC scenarios can be run steady state. [GRD §1.1]

3.2.1.4.3.3.1.2  High Current, Double Null (HC) Scenario

Performance Requirement.

PF coil currents required for plasma initiation and discharge evolution for the HC scenario shall be as defined in Table 10.1-14.

3.2.1.4.3.3.1.3  Low Current, Double Null (LC) Scenario

PF coil currents required for plasma initiation and discharge evolution for the LC scenario shall be as defined in Table 10.1-15.  PF coil envelopes and coil centers (at operating temperature) assumed for generating the PF coil currents are provided in Table 10.1-1.

3.2.1.4.3.3.2  Flexibility

3.2.1.4.3.3.2.1  Double Null Divertor Operation

Description.

PF coil current requirements are provided in subsequent sections for operation with a positive plasma current.  PF coil current requirements for operation with a negative plasma current and a negative TF field are the opposite of the PF coil currents listed for operation with a positive plasma current and a positive TF field.  Likewise, PF coil current requirements for operation with a negative plasma current and a positive TF field are the opposite of the PF coil currents listed for operation with a positive plasma current and a negative TF field.

Performance Requirement.

The tokamak shall be designed, and ancillary systems and facilities shall be capable of being upgraded, to provide flexibility in li and bN in a double null divertor configuration at full toroidal field (-4T and +4T) over a range of plasma currents (between -2MA and +2MA).  [GRD §1.2.1]

3.2.1.4.3.3.2.1.1  Full Current Operation

	a)  Equilibrium conditions shall be sustainable in steady state in each of the states shown in Table 3.2.1.4.3.3.2.1.1 while satisfying requirements for radial position, vertical position, and strike point control.  [GRD §1.2.1.1]

Table 3.2.1.4.3.3.2.1.1 Full Current Operation States

li(3)	bN	
0.4	5	
0.5	2.2	
0.7	0	
1.2	0	
1.2	5	

	b)  Specifically, PF coils shall be capable of providing the PF coil currents listed in:

1.	Tables 10.1-2 and 10.1-3 for nominal operation at -4T and +4T;
2.	Tables 10.1-4 and 10.1-5 for radial position control at -4T and +4T;
3.	Tables 10.1-6 and 10.1-7 for strike point position control at -4T and +4T;
4.	Tables 10.1-8 and 10.1-9 for vertical position control at -4T and +4T.
	
3.2.1.4.3.3.2.1.2  q=5 Operation

	a)  Equilibrium conditions shall be sustainable in steady state in each of the states shown in Table 3.2.1.4.3.3.2.1.2. [GRD 1.2.1.2]

Table 3.2.1.4.3.3.2.1.2  q=5 States

li(3)	bN	
0.4	7	
0.4	5	
0.7	0	
1.5	0	
1.5	7	

	b)  Specifically, PF coils shall be capable of providing the PF coil currents listed in Tables 10.1-10 and 10.1-11 for operation at -4T and +4T.

3.2.1.4.3.3.2.2  Single Null Divertor Operation

	a)  The tokamak shall be designed, and ancillary systems and facilities shall be capable of being upgraded, to provide flexibility in a single null divertor configuration (with active separatrix locations above and below the midplane) in li and bN at full toroidal field (-4T and +4T) over a range of plasma currents (between -2MA and +2MA).

	b)  Equilibrium conditions shall be sustainable in steady state in each of the states shown in Table 3.2.1.4.3.3.2.2.  [GRD §1.2.2]

Table 3.2.1.4.3.3.2.2  Single Null Divertor Operation States

li(3)	bN	
0.4	5	
0.5	2.2	
0.7	0	
1.2	0	
1.2	5	

	c)  Specifically, PF coils shall be capable of providing the PF coil currents listed in Tables 10.1-12 and 10.1-13 for operation at -4T and +4T.

3.2.1.4.3.3.3  Equilibrium Control

The feedback equilibrium control systems for radial, vertical, and separatrix plasma position control shall be independent (i.e. while one position control changes the other two position controls are maintained).(TBR)

3.2.1.4.3.3.3.1  Radial Plasma Position Control

	a)  Control coils shall be provided inside the vacuum vessel for fast (<100ms) radial position control to minimize eddy current heating in the TF and PF coils and support structure.

	b)  The PF coils shall provide slow (>100ms) radial position control.  The control coils and PF coils shall work in conjunction to effect control on intermediate time scales.

	c)  The device shall include a feedback equilibrium control system which provides radial plasma position control such that:

1.	the radial location of the separatrix at the outboard midplane can be maintained within 1 cm (rms displacement) of the nominal position, and
2.	the radial location of the separatrix at the outboard midplane can be returned within 15 ms to within 1 cm of the nominal position in response to instantaneous 20% drops in stored plasma energy every 100 ms (with reheating in between, characteristic of ELMs), in response to needs for RF coupling, and
3.	the radial location of the separatrix at the outboard midplane can be returned to its nominal position after an instantaneous 50% drop in stored plasma energy, characteristic of minor disruptions, while simultaneously maintaining vertical position control once per discharge, and
4.	the radial location of the separatrix at the outboard midplane can be positioned at any location within ±2 cm of its nominal position with a response time of 50 msec.

	d)  Coil current and voltage requirements for controlling the radial location of the separatrix at the outboard midplane in response to instantaneous 20% drops in stored plasma energy every 100 ms shall be as specified  in Table 10.1-21.

	e)  Coil current and voltage requirements for controlling the radial location of the separatrix at the outboard midplane in response to instantaneous 50% drops in stored plasma energy shall be as specified  in Table 10.1-22.

	f)  Coil current and voltage requirements for positioning the radial location of the separatrix within ±2 cm of its nominal position with a response time of 50 msec shall be as specified  in Table 10.1-23.

	g)  PF coils shall be designed to satisfy radial position control requirements for the full range of equilibrium conditions identified in the flexibility Section 3.2.1.4.3.3.2. [GRD §1.8.1]

	h)  Power systems shall be designed to satisfy radial position control requirements attendant with the reference scenarios per Section 3.2.1.4.3.3.1. [GRD §1.8.1]

3.2.1.4.3.3.3.2  Vertical Plasma Position Control

	a) Conducting structure shall be provided which makes the growth rate of the vertical instability, less than 0.2ts, where ts is the L/R time constant of the lowest order, up-down anti-symmetric mode in the conducting structure for all the equilibrium conditions required per the flexibility Section 3.2.1.4.3.3.2. [GRD §1.8.2]

	b) Control coils shall be provided inside the vacuum vessel for fast (<100ms) vertical position control, to minimize eddy current heating in the TF and PF coils and support structure. [GRD §1.8.2]

	c) The device shall include a feedback equilibrium control system which will provide vertical position control such that:

1.	the plasma can be vertically positioned to any location within ±3cm of the midplane with a response time of 5s using one pair of external PF coils and
2.	the plasma vertical position can be controlled within 1cm (rms displacement) of the nominal location on the time scale of the vertical instability growth time using internal control coils. 

where the vertical position of the plasma is defined as the midpoint of the separatrix (last closed flux surface) z-coordinates at a radius of 2.531m, the radial location of the toroidal limiter horizon. [GRD §1.8.2]

	d) PF and control coils shall be designed to satisfy vertical position control requirements for the full range of equilibrium conditions identified in the flexibility Section 3.2.1.4.3.3.2. [GRD §1.8.2]

	e) The coil current and voltage requirements for maintaining vertical plasma position control shall be as specified in Table 10.1-24.

	f) Power systems shall be designed to satisfy vertical position control requirements attendant with the reference scenarios per Section 3.2.1.4.3.3.1. [GRD §1.8.2]

3.2.1.4.3.3.3.3  Separatrix Position Control

	a)  The device shall include a feedback equilibrium control system which provides outboard strike point position control such that:

1.	the location of the outboard strike point can be moved ±5cm along the divertor surface with a response time of 5s and
2.	the location of the outboard strike point can be maintained within ±1 cm of nominal.
3.	Coil current and voltage requirements for moving the location of the outboard strike point ±5cm with a response time of 0.5 s are provided in Table 10.1-25.

	b)  PF and control coils shall be designed to satisfy outboard strike point control requirements for the full range of equilibrium conditions identified in the flexibility Section 3.2.1.4.3.3.2. [GRD §1.8.3]

	c)  Power systems shall be designed to satisfy outboard strike point control requirements attendant with the reference scenarios per Section 3.2.1.4.3.3.1. [GRD §1.8.3]

3.2.1.4.3.3.3.4  External Kink Mode Control

	a) Control coils shall be provided inside the vacuum vessel for active feedback control of non-axisymmetric plasma instabilities.

	b) These coils shall be divided toroidally into four segments that can be independently powered to provide non-axisymmetric control fields, and may be the same coils as are used for fast radial and vertical control.

	c) A conducting structure shall be provided for the purpose of passively stabilizing the ideal external kink mode for all the equilibrium conditions required per the flexibility Section 3.2.1.4.3.3.2. [GRD §1.8.5]
  
	d) The conducting structure shall be compatible with the initial complements of heating systems per the plasma heating and current drive Section 3.2.1.4.6. [GRD §1.8.5]

	e) Flexibility to reconfigure the structure by removing and re-installing elements of it, including the ability to make it compatible with the upgrade complements of heating systems per the plasma heating and current drive Section 3.2.1.4.6, shall be provided. [GRD §1.8.5]

3.2.1.4.3.4  Field Errors

3.2.1.4.3.4.1  System Field Error Requirements

	a) n=1 Field Errors.  A system of non-axisymmetric FEC coils shall be provided to compensate for intrinsic field errors with toroidal harmonic number n equal to 1 from all sources (including coil misalignment, bus work, coil feeds, coil crossovers, and magnetic materials) in order to control thresholds for locked modes.  Required characteristics of the FEC coils are provided in Section 3.7.9.1.

The FEC coils shall be capable of reducing the amplitudes of the m=1,2,3,4; n=1 Fourier components of the magnetic field to within the following limits calculated per the methodology described in paragraph 6.2.

	b) n=2 Field Errors.  The intrinsic field errors with toroidal harmonic number n equal to 2 from all sources (including coil misalignment, bus work, coil feeds, coil crossovers, and magnetic materials) shall be such that the amplitudes of the m=3,4,5 Fourier components of the magnetic field are limited to:

3.2.1.4.3.4.2  FEC Coil Current Requirements

FEC coils shall be designed to provide a maximum current of TBD kA-turns.

3.2.1.4.3.4.3  Field Error Requirement and FEC Coil Current Allocations

Description.  

Several sources of field error have been identified, some of which can be compensated by the FEC coils and some of which cannot.  Field errors which cannot be compensated by the FEC coils include:

•	field errors due control currents in the Fast Plasma Position Control (FPPC) coils and associated eddy currents in the passive structures;
•	field errors due to the FEC coils.

Field errors which can be compensated by the FEC coils include:

•	field errors due to magnetic materials;
•	field errors due to TF and PF coils.

Performance Requirements.

The system field error requirements (defined in Section 3.2.1.4.3.4.1) and the FEC coil current requirement (defined in 3.2.1.4.3.4.2) shall be allocated to TPX subsystems as shown in Table 3.2.1.4.3.4.3.

Table 3.2.1.4.3.4.3  Field Error Allocations

WBS Identifier	

Subsystem	
n=1, 2
Allocations	FEC Coil Current
Allocations	
11	Plasma Facing Components (PFC)	16%	0%	
12	Vacuum Vessel (VV) System 	2%	0%	
13	Toroidal Field (TF) System	8%	14%	
14	Poloidal Field (PF) System	32%	57%	
191	Field Error Correction (FEC) Coil System	8%	0%	
192	Fast Plasma Position Control (FPPC) Coil System	8%	0%	
21	Neutral Beams	2%	3%	
34	Vacuum Pumping	2%	3%	
71	Building, Modifications, and Site Improvements	2%	3%	
	Unallocated	20%	20%	
	Total	100%	100%	

3.2.1.4.4  Power Handling

3.2.1.4.4.1  Scrape-off Layer (SOL) Envelopes

	a) The +2cm flux surface shall intercept only the outboard divertor targets for the range of equilibria defined in the Double Null Divertor Operation section 3.2.1.4.3.3.2.1.  All internal hardware must be located accordingly. [GRD §1.3.1]

	b) The -2.5cm flux surface shall intercept only the inboard divertor targets for the range of equilibria defined in the Double Null Divertor Operation section 3.2.1.4.3.3.2.1.  All internal hardware must be located accordingly. [GRD §1.3.1]

	c) The +2cm flux surface shall intercept only the inboard and outboard divertor targets for the range of equilibria defined in the Double Null Divertor Operation section 3.2.1.4.3.3.2.1.  All internal hardware must be located accordingly. [GRD §1.3.1]

3.2.1.4.4.2  Maximum Heating Power

Plasma facing components shall be designed to accommodate heat loads associated with a maximum steady state heating power of 45MW [GRD §1.3.2]

3.2.1.4.4.3  Power Partitioning

Description.

The high core radiation condition results in the maximum heat loads for equipment located near the midplane.  The low core radiation condition results in maximum heat loads to the divertors.  The divertor power handling requirements are driven by the power partitioning for double null operation.  Therefore the maximum steady state heating power for single null operation may be less than the maximum steady state heating power for double null operation. [GRD §1.3.3]

Performance Requirement.

Plasma facing components shall be designed to accommodate the steady state heat loads associated with a high core radiation condition and a low core radiation condition as specified in figures 3.2.1.4.4.3-1 and -2 below. [GRD §1.3.3]

Figure 3.2.1.4.4.3-1 Power Partitioning for High Core Radiation Condition

Figure 3.2.1.4.4.3-2 Power Partitioning for Low Core Radiation Condition

3.2.1.4.5  Disruption Handling

The system shall be designed to accommodate each of the major disruption types characterized within Table 3.2.1.4.5.

Table 3.2.1.4.5 Disruption Characteristics

Disruption Type	Characterized By One or More of the Following	
I	  •	possible vertical displacement
  •	a plasma thermal quench occurring in 0.1‑1 ms
  •	a current decay with a time-varying decay rate, such that the peak rate is less than or equal to 1.25 MA/ms, and the average rate is less than or equal to 0.5 MA/ms.  The average rate is determined by the time to decay from 90% to 10% of the pre-disruption event.
  •	a peak poloidal halo current up to 660 kA, 33% of the maximum plasma current prior to the disruption, with a toroidal peaking factor of 1.5:1; that is, the toroidal dependence of the halo current is [1 + 0.5cos (f - f0)], for all toroidal phase angles f0  from 0 to 2.
  •	a frequency of occurrence of 49% in any phase or mode of operation. [GRD §1.10]	
II	  •	vertical displacement
  •	a plasma thermal quench occurring in 0.1‑1 ms
  •	a peak poloidal halo current up to 800 kA, 40% of the maximum plasma current prior to the disruption, with a toroidal peaking factor of 2:1; that is, the toroidal dependence of the halo current is [1 + cos (f - f0)], for all toroidal phase angles f0  from 0 to 2.
  •	a frequency of occurrence of 1% in any phase or mode of operation. [GRD §1.10]	

3.2.1.4.6  Plasma Heating and Current Drive

3.2.1.4.6.1  Heating and Current Drive Technologies

The TPX facility shall include a heating and current drive system based on multiple technologies (Neutral Beam (NB), Ion Cyclotron Heating/Fast Wave Current Drive (ICH/FWCD), and Lower Hybrid Heating/Current Drive (LHH/LHCD), each subsystem configured to provide current drive as well as heating, and each expandable to greater power levels. [GRD §1.4]

3.2.1.4.6.2  Flexibility of Current Density Control

Heating and current drive systems shall provide flexibility in the control of current density profiles. [GRD §1.4]

3.2.1.4.7  Operational Requirements

Operational limits for D and DT operation shall be established such that the environmental, safety, and health effects determined for TFTR, as presented in the Environmental Assessment for TFTR, shall not be exceeded during normal operation of TPX. [GRD §2.0]

3.2.1.4.7.1  Pulse Operation

The TPX facility shall initially be configured to provide 1000s pulses with H and D plasmas for the reference scenarios per Section 3.2.1.4.3.3.1 with initial neutron source rates per Section 3.2.6.2.3 and pulse repetition rates per Section 3.2.1.4.7.2.  Unless otherwise qualified, the pulse length refers to the flattop time (i.e. the period of constant plasma current). [GRD §2.1]

3.2.1.4.7.2  Pulse Repetition Rate

	a) In its initial configuration, the TPX facility shall be capable of providing 10 consecutive 1000s pulses at 75 minute pulse intervals in a 24 hour period when operated per the reference scenarios as specified in 3.2.1.4.3.3.1.  The pulse intervals refer to the time between pulse initiations. [GRD §2.2]

	b) In its initial configuration, the TPX facility shall be capable of providing 30 consecutive 100s pulses at 20 minute pulse intervals in a 24 hour period when operated per the reference scenarios as specified in 3.2.1.4.3.3.1. [GRD §2.2]

3.2.1.5  Experiment Shutdown

3.2.1.5.1  Normal Shutdown

Description.

Normal Shutdown includes all system actions necessary to shutdown the plasma and associated subsystems at the conclusion of a shot during experimental operations. (TBR)

Requirement.

The TPX system shall provide the capability to perform a controlled shutdown of the plasma and associated subsystems at the conclusion of shot during experimental operations. (TBR)

3.2.1.5.2  Abnormal Shutdown

Description.

Abnormal shutdown includes all system actions necessary to shutdown the plasma and associated subsystems when a condition occurs during experimental operations that could cause significant damage to the TPX system or cause injury to personnel.  (TBR)
Requirement.

The TPX system shall provide the capability to perform a controlled shutdown of the plasma and associated subsystems if a condition occurs during experimental operation which could cause significant equipment damage or cause injury to personnel.  (TBR)

3.2.1.6  Instrumentation, Control and Data Acquisition

Description.

The I&C system will provide supervision, remote control, monitoring, data acquisition, and data handling for subsystems. [GRD §1.12]

The national perspective of TPX requires that researchers located at the TPX site and at other laboratories and universities have access to the facility in support of the remote operation, physics planning, analysis, and coordination of experimental objectives.  The computations architecture will incorporate distributed computational facilities as important elements in the analysis, storage, and display of control and diagnostic information. [GRD §1.12]

Performance Requirements.  

	a) The TPX facility shall have an instrumentation, control, and data acquisition (I&C) system that allows for coordination of operations and the acquisition, archiving, and display of all pertinent information. [GRD §1.12]

	b) The I&C system shall be designed to accommodate steady state operation of TPX. [GRD §1.12]

	c)  The operations environment shall provide real-time display of information and allow changes to be implemented during the course of a discharge. [GRD §1.12]

	d)  The computations architecture shall support a distributed computing environment spanning a minimum of four geographically separate sites inclusive of Princeton Plasma Physics Laboratory, the local site. [GRD §1.12]

	e)  The selected sites shall be connected via a high performance, wide area computer network, with sufficient bandwidth to allow transmission of information including file transfers, graphical displays, and video information with minimal latency consistent with available technology. [GRD §1.12]

3.2.1.7  Plasma Diagnostics

	a) The TPX machine shall incorporate a system of diagnostics to provide the measurements of the plasma behavior that are necessary to fulfill the physics mission of the TPX project. [GRD §1.11]

	b) Diagnostic measurements shall be provided for plasma control and operational purposes. [GRD §1.11]

	c) All diagnostics shall be implemented consistent with achievable viewing access and state-of-the-art measurement techniques. [GRD §1.11]

	d) Diagnostics shall be designed for D operation only.  In the event of DT operation, an upgrade of selected systems will be required to accommodate radiation hardening and/or radiation shielding. [GRD §1.11]

3.2.1.8  Facility Shutdown

Description.

Facility shutdown involves the shutdown of TPX equipment that is not part of the experiment shutdown in Section 3.2.1.5.  This includes shutdown of infrastructure subsystems like power, water, and ECS as well as other subsystems such as diagnostics, and I&C.(TBR)

Performance Requirement.

The TPX system shall provide the capability to perform a controlled shutdown of the facility.(TBR)

3.2.1.9  Tokamak Fuel

3.2.1.9.1  Gas Injection

The device shall be provided with a programmable gas injection system capable of supplying H, D, and other gases to the outboard midplane and various locations in the divertor regions with a maximum throughput of 250 Torr-l/s. [GRD §1.5.1]

3.2.1.9.2  Pellet Injection

The device and facility shall be capable of accommodating a pellet injection system capable of injecting H or D pellets with a maximum steady state fueling rate of 85 Torr-l/s. [GRD §1.5.2]

3.2.1.10  System Cooling

The system shall be capable of providing sufficient cooling capability to accommodate the heat loads associated with pulse operations (per 3.2.1.4.7) as specified in Table 3.2.1.10.

3.2.1.11  System Power

Using the input power identified in Table 3.1.5.1, the system shall be capable of providing the baseline power levels specified in Table 3.2.1.11.

3.2.1.11.1  Allowable Voltage Variation

	a)  Variations to the voltage incoming to PPPL shall be limited to ± 3 percent.

	b)  Variations to the voltage at the nearest point of connection to other utility customers shall be limited to ± 1 percent.

3.2.2  System Capability Relationships

N/A.

3.2.3  External Interface Requirements

The system will interface with the following external systems:

3.2.3.1  Commercial Power Interface

The system shall interface with the existing electrical utility as specified in paragraph 3.1.5.1.

3.2.3.2  Local Water Interface

TPX shall interface with the local water supply as specified in Table 3.1.5.2.

Table 3.2.1.10  Subsystem Heating Loads

Subsystem	Heat Load at User per Mode of Opereration1 (MW)	
WBS		I	II	
11	PFCs	18.000	45.000	
18	Tokamak Shielding	3.720	3.720	
19	FPPC/FEC	1.980	1.980	
231	ICH Antenna	0.365	0.665	
232	ICH Tuning & Matching	0.300	0.900	
241	LH Coupler	0.320	0.790	
62	Plasma Diagnostics	0.010	0.073	
Total 1	24.695	53.128	
21	Neutral Beam Injection - Beam Line	25.000	75.000	
21	Neutral Beam Injection - Ion Source	2.000	6.000	
234	ICH Transmitters	9.000	18.000	
243a	RF Klystons	5.660	11.300	
4Xa	Power Systems (TF, PF, Bus)	3.300	3.300	
Total 2	44.960	113.600	
21	Neutral Beam Injection - Power Supplies	11.000	33.000	
233	ICH Transmission Lines	0.600	1.200	
242 & 243b	RF Components	1.220	2.440	
34	Vacuum Pumping Systems	0.254	0.254	
Total 3	13.074	36.894	
4X b	Power Systems - MG Set	3.500	3.500	
72	Cryogenic Systems	5.000	15.000	
7X?	Facility	6.000	6.000	
Total 4	14.500	24.500	
Total Pulse Operation	82.475	203.368	
Total Non-Pulse2	14.754	24.754	
TOTAL	97.2	228.1	
1  I=Pulse operation at 18 MW; II=Pulse operation at 45 MW
2 Non-pulse operation includes the sum of Total 4 and vacuum pumping

Table 3.2.1.11  TPX System Power

Load	MVA	p.f.	MW	MVAR	
Base Load	43.9	0.78	34.27	27.43	
Pulsed Load	73.62	0.89	65.64	33.33	
Peak Load	116.94	0.85	99.91	60.76	

3.2.3.3  Data Processing and Remote I&C Interface

TPX shall provide command feedback and experimental data for data processing and Remote I&C. (TBR).

3.2.4  Physical Characteristics

3.2.4.1  System Configuration

TPX system elements within the cryostat shall conform to the space envelope constraints specified in the drawings included in Table 3.4.2.1.

Table 3.2.4.1  System Configuration Drawings

System Element	Applicable System Configuration Drawings	
TBD	TBD	

3.2.5  System Quality Factors

3.2.5.1  Reliability

3.2.5.1.1  Mission Reliability

Provisions for recovery shall be made for every failure mode which has a reasonable probability (P) of occurrence (P≥10-4) over the life of the device or has a low probability of occurrence (10-4>P≥10-6) over the life of the device and no exemption from the Project based on cost/risk/benefit considerations and which, directly or indirectly, would compromise the required operational capability of the device and facility.  The mission reliability requirement only applies prior to injecting tritium into the tokamak.  [GRD §3.1]

3.2.5.1.2  Shot Reliability

The shot reliability for the TPX system shall be greater than 90%.  The applicable shot reliability time for the equipment in a subsystem begins when the equipment shot functions start and ends when the equipment shot functions end (TBR).  The shot reliability requirement only applies prior to tritium being injected into the tokamak.  [GRD §3.3]

3.2.5.1.2.1  Subsystem Shot Reliability

The TPX Subsystems shall meet the allocated subsystem shot reliability requirements provided in Table 3.2.5.1.2.1.

3.2.5.2  Maintainability

TPX shall incorporate maintainability features in the design which are consistent with achieving the mission reliability, operational availability, and scheduled maintenance requirements stated herein. Maintainability requirements only apply prior to tritium being injected into the tokamak. [GRD §3.4]

3.2.5.2.1  Scheduled Maintenance

The time during which the device is unavailable due to scheduled maintenance shall not exceed one week per three operating weeks averaged over a 32 week run period.  Periods during which the device is unavailable due to reconfiguration or modification do not contribute to the scheduled maintenance downtime. [GRD §3.5]

3.2.5.2.2  Remote Maintenance

Remote maintenance capability shall be provided such that personnel exposure during maintenance operations do not exceed PPPL administrative limits.  Provisions for remote maintenance shall be made for all equipment inside the vacuum vessel and for ex-vessel equipment which will be come activated to the point where hands-on maintenance would result in PPPL administrative limits being exceeded.

Table 3.2.5.1.2.1 Shot Reliability Allocations

WBS Identifier	Subsystem	Shot Reliability	
11	Plasma Facing Components (PFC)	0.9944	
12	Vacuum Vessel (VV) System 	0.9965	
13	Toroidal Field (TF) System	0.9958	
14	Poloidal Field (PF) System	0.9951	
15	Cryostat	0.9979	
16	Tokamak Support Structure	0.9993	
18	Tokamak Shielding	0.9979	
19	Field Error Correction (FEC) and Fast Plasma Position Control (FPPC) Coil Systems	0.9965	
21	Neutral Beam System	0.9944	
23	Ion Cyclotron Heating and Fast Wave Current Drive	0.9944	
24	Lower Hybrid Heating and Current Drive	0.9944	
31	Fuel Storage and Delivery	0.9979	
33	Radiation Monitoring and Tritium Cleanup	0.9993	
34	Vacuum Pumping	0.9965	
4	Power Systems	0.9958	
61	Central I&C	0.9944	
62	Diagnostics	0.9944	
71	Building, Modifications, and Site Improvements	0.9995	
72	Cryogenic Systems	0.9972	
73	Heating and Cooling Systems	0.9986	
74	Test Cell Penetrations	0.9998	
	Random Failures	0.9322	
	Other Initiators	0.9655	
	Total	0.9000	

3.2.5.2.3  Hands-on Maintenance

The TPX design shall accommodate hands-on maintenance under the following conditions:

	a)  Within two weeks of shutdown of all equipment except the ICH/FWCD launcher, for the first two years of operation

	b)  Inside the vacuum vessel following a one year of shutdown during which activated in-vessel components, which would otherwise preclude personnel access inside the vacuum vessel, would be remotely removed.

	c)  Incorporating radiation shielding to permit hands-on maintenance within two weeks of shutdown of all equipment outside the shield boundary except for major components such as TF coils, VV sectors, and lower PF ring coils which might require tokamak disassembly.

3.2.5.2.3.1  ICH/FWCD Hands-on Maintenance

The ICH/FWCD launcher shall be capable of being shielded to permit hands-on maintenance of all other equipment within two weeks of shutdown for the first two years of operation.

3.2.5.2.4  TPX Assembly and Disassembly

The tokamak shall be capable of being disassembled and reassembled following a one year of shutdown during which activated in-vessel components which would otherwise preclude personnel access inside the vacuum vessel, would be remotely removed.

3.2.5.2.5  Two Man Lift Limits

Assemblies which exceed two man manual lift limits shall include provisions for lifting eyes or other sling attach provisions.

3.2.5.2.6  Failure of Fault Detection Equipment

Failure of diagnostic system fault detection components shall not introduce failure of operational equipment.

3.2.5.2.7  Accessibility of Test Points

To the extent determined cost effective and consistent with the repair approach, test points shall be accessible to permit fault isolation and checkout to the piece part level without disassembly of the component except for removal of covers for test point access.

3.2.5.2.8  Access to Panels

When performance of emergency or unscheduled maintenance requires wear of protective equipment, the design of controls, access panels and maintenance equipment shall provide adequate access.

3.2.5.2.9  Mean Down Time

The mean down time (MDT) for unscheduled maintenance shall be consistent with system availability requirements.  

3.2.5.2.10  Decontamination and Disposal

The design of the system and its associated facilities shall accommodate the need to decontaminate tools and equipment and the ultimate disposal of the system.

3.2.5.3  Availability

TPX shall be designed to achieve an operational availability of at least 75% when operated per the reference scenarios of 3.2.1.4.3.3.1 with pulse repetition rates per 3.2.1.4.7.2.  Availability is defined as the ratio of the number of shots in an operational run period in which the device is operational at its rated performance level for the planned duration of the shot to the number of shots which could be achieved during that run period in the absence of component failures and software errors.  The system level operational availability (OAs) is a function of equipment MTBF and failure modes during steady state operation and repair/restoration times for applicable failure modes.  AOs is calculated as the product of all of the subsystem availabilities, OAi, where OAi is the operational availability for equipment i.  Delays attributable to physics planning do not impact operational availability as defined herein.  Delays attributable to low probability events for which provisions for recovery are not required, do not impact operational availability as defined herein.  This availability requirement only applies prior to injecting tritium into the tokamak. [GRD §3.2]

3.2.5.3.1  Subsystem Availability

TPX subsystems shall meet the allocated subsystem operational availability requirements provided in Table 3.2.5.3.1 when operated per the reference scenarios of 3.2.1.4.3.3.1 with pulse repetition rates per 3.2.1.4.7.2.  

[Note:  Subsystem availability is not normally specified.  Instead a subsystem level mean time between failure (MTBF) and mean time to repair (MTTR) is specified based on the results of system level reliability analysis.  That analysis should result in the development of subsystem MTBFs and MTTRs which will support the desired subsystem availability.  If these actions are taken, the following formula can be used to calculate subsystem availability:  OAi = MTBF / MTBF+MDT.  The value for MDT will be failure mode specific and will include the value for the MTTR as well as any other delay times such as for cryostat cool down. These other delay times would be provided by Project systems engineering to the subsystem developer to support their reliability and availability analyses.]

Table 3.2.5.3.1 Operational Availability Allocations

WBS	
Subsystem	Operational Availability
%	
11	Plasma Facing Components (PFC)	94.8	
12	Vacuum Vessel (VV) System 	97.9	
13	Toroidal Field (TF) System	97.0	
14	Poloidal Field (PF) System	96.5	
15	Cryostat	98.7	
16	Tokamak Support Structure	99.5	
18	Tokamak Shielding	98.9	
19	Field Error Correction (FEC) and Fast Plasma Position Control (FPPC) Coil Systems	97.9	
21	Neutral Beam System	98.6	
23	Ion Cyclotron Heating and Fast Wave Current Drive	98.6	
24	Lower Hybrid Heating and Current Drive	98.6	
31	Fuel Storage and Delivery	99.7	
33	Radiation Monitoring and Tritium Cleanup	100.0	
34	Vacuum Pumping	98.3	
4	Power Systems	99.9	
61	Central I&C	99.98	
62	Diagnostics	99.3	
71	Building, Modifications, and Site Improvements	100.0	
72	Cryogenic Systems	99.8	
73	Heating and Cooling Systems	99.9	
74	Test Cell Penetrations	99.997	
	Random Failures	78.9	
	Other Initiators	93.8	
	Total	75.0	

3.2.5.4  Additional Quality Factors

3.2.5.4.1.1  Annual Operating Limits

In any year  when operated per the reference scenarios specified in paragraph 3.2.1.4.3.3.1 and prior to injecting tritium into the tokamak, the design shall allow for up to: [GRD §2.3]

	a) 3,000 pulses
	b) 2x105s of D operation
	c) 5x105s of total operation

3.2.5.4.1.2  Lifetime Operating Limits

	a) All TPX systems, with the exception of the divertor modules, shall be designed for the number of cycles and operating time attendant with a 10 year operating life. [GRD §2.4]

	b) New building and utilities shall be designed for a 25 year operating life from the start of plasma operations. [GRD §2.4]

	c) When operated per the reference scenarios specified in paragraph 3.2.1.4.3.3.1 and based on the factors for fatigue life specified in the TPX Structural and Cryogenic Design Criteria Document, the design shall allow for up to:  [GRD §2.4]

		1. 30,000 pulses
		2. 2x106s of D operation
		3. 5x106s of total operation

3.2.6  Environmental Conditions

The system shall meet all of the requirements of 3.2.1 and 3.7 when exposed to the natural, induced, and abnormal environments identified below.

3.2.6.1  Natural Environments

Natural environments include those to which TPX facilities will be exposed to and TPX components and support equipment are exposed to during transportation and handling.

3.2.6.1.1  Temperature (Drybulb)

	a) Non-Operating.  Transportation and handling temperature environments shall be -66 (TBR) to +53 (TBR) degrees Celsius for periods up to 30 (TBR) days.  The non-operating temperature environments for storage of equipment are -66 (TBR) to +53 (TBR) degrees Celsius for (TBD) days.

	b)  Operating:  Operating temperature environments external to TPX site facilities shall be -66 (TBR) to +53 (TBR) degrees Celsius.

3.2.6.1.2  Humidity

The non-operating and operating humidity environments for the TPX and support equipment are 0 to 100 percent relative humidity (RH) (TBR) at temperatures up to 27 degrees Celsius (TBR).

3.2.6.1.3  Fungus Growth

The non-operating and operating fungus growth environment within TPX site facilities consists of fungus growth occurring on nutrient organic materials including contamination from greases, oils, and dust for all conditions exceeding 60 percent RH (TBR) and 16 degrees Celsius (TBR).

3.2.6.1.4  Sand and Dust

The non-operating and operating sand and dust environment external to TPX site facilities consists of particle diameters ranging from (TBD) to 0.3 mm (TBR) with a density of no more than TBD.

3.2.6.1.5  Wind

Wind environments as specified below.  The wind load design and evaluation guidelines for important/low hazard facilities described in Chapter 5 of UCRL-15910 shall be employed.

	a)  Sustained wind speeds not exceeding TBD m/s.

	b)  Gusts not exceeding TBD m/s.

	c)  Extreme wind (most probable tornado) with a maximum wind speed of 110 mph, maximum pressure drop of 0.27 psi, and maximum rate of pressure drop of 0.06 psi/sec.

3.2.6.1.6  Lightning

Lightning strike as defined by the levels in Figure 3.2.6.1.6.

Figure 3.2.6.1.6  Lightning Strike Current Model Waveform - 2 % Exceedence Level Model

3.2.6.1.7  Seismic

The design base earthquake (DBE) is defined as a peak horizontal ground acceleration of not exceeding 0.13g for performance category 2 (PC-2) system elements and not exceeding 0.09g for PC-1 elements.  The vertical component of ground motion is defined as two-thirds of the horizontal component.  PC designations are as shown in Table 3.2.6.1.7.  Other system elements shall be designed to general facility requirements in accordance with UCRL-15910.

3.2.6.1.8  Solar Heating

Solar heating of 307 (TBR) BTU/ft2/hr at noon and 0 (TBR) BTU/ft2/hr at midnight.

3.2.6.1.9 Atmospheric Pressure

Atmospheric pressures between 503 (TBR) and 1080 (TBR) mb.

Table 3.2.6.1.7  Performance Class Designations

System Element	Performance Class	
WBS 1 - Tokamak Systems	2	
WBS 2- Auxiliary Heating and Current Drive Systems	2	
WBS 3 - Fueling and Vacuum Systems	2	
WBS 4 - Power Systems	0	
WBS 5 - Maintenance Systems	2	
WBS 6 - Data Systems	0	
WBS 7 - Cryogenic and Water Cooling Systems	0	
WBS 8 - Facilities	1	

3.2.6.2  Induced Environments

Induced environments include those to which the TPX and support equipment are exposed during transportation and handling as well as during operations within the Test Cell building and site facilities.

3.2.6.2.1  Vibration

The maximum vibration environment for which the system shall be protected against is (TBD).

3.2.6.2.2  Shock

	a)  Non-Operating:  The non-operating shock environments are as defined in MIL-STD-810. The maximum shock environment for equipment experiencing shipping and handling is specified in Figure (TBD).

	b)  Operating:  The operational shock environment is TBD.

3.2.6.2.3  Neutron Source Rates/Yields

	a) The TPX facility shall be designed to accommodate heat loads attendant with the peak neutron source rate initially envisioned for D operation defined in Table 3.2.6.2.3 below at the pulse repetition rates specified in Section 3.2.1.4.7.2. [GRD §2.5]

	b) Tokamak systems shall be designed for and the facility be capable of being upgraded for the heat loads attendant with the peak neutron source rate ultimately envisioned for D operation in steady state operation specified in Table 3.2.6.2.3 below. [GRD §2.5]

3.2.6.3  Abnormal Environments

3.2.6.3.1  Missile Impact

Important/low hazard buildings shall be designed to withstand the impact of a 11,300 lb aircraft traveling at 195 mph.

3.2.7  Transportability

All assemblies and components shall be transportable by commercial carrier via highway, air, sea, or railway in accordance with the requirements of MIL-STD-1367 (TBR). All system elements that are unsuitable, due to operational or functional characteristics, for normal transportation methods by highway, air, or railway shall be identified.

Table 3.2.6.2.3  Neutron Source Rates/Yields for D and DT Operation

	Units	DD Neutrons	DT Neutrons	
D Operation				
Peak neutron source rate				
Initial capability (Peak neutron source rate initially envisioned for D operation)	s-1	5.0x1016	1.0x1015	
Ultimate capability (Peak neutron source rate ultimately envisioned for D operation)	s-1	7.5x1016	2.25x1015	
Average annual neutron source rate				
      	Year 1	s-1	0.75x1016	0.75x1014	
      	Year 2	s-1	1.50x1016	2.25x1014	
      	Year 3	s-1	2.25x1016	4.50x1014	
      	Years 4-10	s-1	3.00x1016	6.00x1014	
	Maximum annual neutron yield				
      	Year 1		0.5x1020	0.5x1018	
      	Year 2		2.5x1020	3.75x1018	
      	Year 3		1.5x1021	3.0x1019	
      	Year 4		3.0x1021	6.0x1019	
      	Years 5-10		6.0x1021	1.2x1020	
	Maximum total neutron yield		4x1022	8x1020	
DT Operation				
Peak neutron source rate (corresponds to DT fusion power of 15MW)	s-1	6.4x1016	5.3x1018	

3.2.8  Flexibility and Expansion

The TPX equipment and support equipment shall be designed to accommodate major system reconfiguration, repair, and internal and external maintenance requirements.  Consideration shall be given to flexibility and expansion for subsystems and components for which the design is evolving or for which expansion of functional capabilities must be included.  These include:  Short-pulse DT operation at the end of the experiment;  Remote maintenance after the first two years of operation;  Power systems, including backup power;  Cryogenic and water cooling systems;  Instrumentation and Control system, including interface with the wide area network and bandwidth requirements.

3.2.8.1  Accommodation of Future Startup Scenarios

	a)  The device and facility shall be designed to accommodate upgrades capable of inductively initiating a 1MA inductive discharge scenario with a preprogrammed startup sequence as described in 3.2.1.4.2.3, except that the breakdown voltage is increased to 20V, the avalanche period is 5ms, and the radius of the null region is 0.2m.

	b)  PF and IC coil currents appropriate for a 20V voltage breakdown shall be as provided in Table 10.1-16.

3.2.8.2  Accommodation of  Vacuum Pumping Rate Upgrades

3.2.8.2.1  Neutral Pressure Vacuum Pumping Rate Upgrade

The TPX facility shall be capable of being upgraded to provide a vacuum pumping rate of 100 torr‑l/sec with a neutral pressure of 1.2 mtorr at the entrance to the vacuum pump duct. [GRD §1.3.7]

3.2.8.2.2  Maximum Pumping Rates Upgrade

	a) The TPX facility shall be capable of being upgraded for maximum vacuum pumping rates of 100 torr-l/s when operated at the pulse repetition rates specified in Section 3.2.1.4.7.2 and 250 torr-l/s when operated at lower pulse repetition rates. [GRD §1.3.7]

	b) The TPX facility shall be capable of being upgraded for a maximum vacuum pumping rate of 100 torr-l/s in steady state operation. [GRD §1.3.7]

3.2.8.2.3  Minimum Vacuum Pumping Speed Upgrade

The TPX facility shall be capable of being upgraded to provide a minimum vacuum pumping speed of 85,000 l/sec. [GRD §1.3.7]

3.2.8.3  Accommodation of Plasma Heating and Current Drive Upgrades

3.2.8.3.1  Electron Cyclotron Heating/Current Drive Upgrade

Description.

The ability to accommodate the addition of ECH/ECCD is required to provide a backup approach for start-up assist, discharge cleaning, electron heating, and localized current profile control. [GRD §1.4.4]

3.2.8.3.1.1  10 MW ECH/ECCD Power

The device and facility shall be configured to accommodate an upgrade to 10 MW of ECH/ECCD power to the plasma at 110 GHz through one horizontal port otherwise assigned to other heating systems or diagnostics. [GRD §1.4.4]

3.2.8.3.1.2  ECH/ECCD Capabilities

The upgrade ECH/ECCD system shall provide the capability to vary poloidal and toroidal launch angles and to control the wave polarization. [GRD §1.4.4]

3.2.8.3.2  Neutral Beam Power Upgrade to 24MW

The device and facility shall be capable of accommodating 24MW of neutral beam power to the plasma (two co-directed TFTR beamlines plus one counter-directed TFTR beamline modified for 1000s pulse lengths) together with upgraded complements of ICH/FWCD and LHCD. [GRD §1.4.1]

3.2.8.3.3  ICH/FWCD Upgrades

3.2.8.3.3.1  ICH/FWCD Power Upgrade to 18 MW

	a)  The device and facility shall be configured to accommodate an upgrade to 18 MW of ICH/FWCD power to the plasma, together with the upgraded complements of NB and LHH/LHCD specified herein. [GRD §1.4.2]

	b) The upgrade ICH/FWCD power shall be coupled to the plasma through three launchers located in adjacent ports. [GRD §1.4.2]

3.2.8.3.3.2  ICH/FWCD Operating Frequency Upgrade

The ICH/FWCD shall be capable of being upgraded (by changing tuning and matching elements outside the plasma vacuum boundary) to operate at any frequency in the range of 40‑80 MHz. [GRD §1.4.2]

3.2.8.4  Upgrade to Steady State Operation

3.2.8.4.1  Steady State Operation

The tokamak shall be designed for and the facility be capable of being upgraded for steady state operation with H and D plasmas for the full range of flexibility specified in Section 3.2.1.4.3.3.2  with the ultimate neutron source rates specified in Section 3.2.6.2.3. [GRD §2.1]

3.2.8.4.2  Steady State Neutral Beam Power

The total neutral beam power required for steady state operation is 8MW in the direction of positive plasma current, to allow co-directed beamlines to be operated sequentially.  All other heating and current drive systems have the same performance requirements in steady state as in the initial configuration. [GRD §2.1]

3.2.8.4.3  Steady State Cooling Capability

The system shall be capable of being upgraded to provide sufficient cooling capability to accommodate the heat loads associated with steady state operations as specified in Table 3.2.8.4.3.

3.2.8.5  Upgrade for Tritium Operation

The tokamak shall be designed for and the facility be capable of being upgraded for 1s of operation with a DT plasma (with a maximum fusion power of 15MW), obtained by injecting tritium into a fully formed and heated D plasma. [GRD §2.1]

3.2.8.6  External Kink Mode Control Upgrade

Power systems shall be capable of being upgraded, if necessary, to power all segments of the non-axisymmetric coils independently at a level compatible with the upgrade requirements for fast radial and vertical position control.

3.2.8.7  Diagnostics Upgrades

The device and facility shall be capable of accommodating the diagnostic upgrades shown in Table 3.2.8.7 below: [GRD §1.11.2]

3.2.9  Portability

N/A.

3.3  Design and Construction

3.3.1  Materials, Processes, and Parts

3.3.1.1  Magnetic Permeability

All materials to be used in the tokamak and peripheral equipment must have a relative magnetic permeability less than 1.02 unless otherwise authorized by the Project.

3.3.1.2  Vacuum Boundary Materials

All materials to be used within the plasma vacuum boundary shall be approved by the Project.

Table 3.2.8.4.3  Steady State Subsystem Heating Loads

WBS/Subsystem	Heat Load at User	
	(MW)	
11	PFCs	45.000	
18	Tokamak Shielding	3.720	
19	FPPC/FEC	1.980	
231	ICH Antenna	0.665	
232	ICH Tuning & Matching	0.900	
241	LH Coupler	0.790	
62	Plasma Diagnostics	0.073	
Total 1	53.128	
21	Neutral Beam Injection -Beam Line	75.000	
21	Neutral Beam Injection -Ion Source	6.000	
234	ICH Transmitters	18.000	
243a	RF Klystons	11.300	
4Xa	Power Systems (TF, PF, Bus)	3.300	
Total 2	113.600	
21	NB-Power Supplies	33.000	
233	ICH Transmission Lines	1.200	
242 & 243b	RF Components	2.440	
34	Vacuum Pumping Systems	0.254	
Total 3	36.894	
4X b	Power Systems - MG Set	3.500	
72	Cryogenic Systems	15.000	
7X?	Facility	6.000	
Total 4	24.500	
Total Pulse Operation	203.368	
Total Non-Pulse1	24.754	
TOTAL	228.1	
1 Non-pulse operation includes the sum of Total 4 and vacuum pumping

Table 3.2.8.7  Diagnostics Upgrade Accommodations

Machine Diagnostics	Physics/Fluctuation Diagnostics	Divertor/Edge Diagnostics	
Steady State Magnetics	Infrared Polarimetry
Impurity Pellet Injector
IR/FIR Multichannel Interferometer
ECE Michelson Interferometer
ECE Grating Polychromator
Millimeter-wave Reflectometer
Collective Wave Scattering
Beam Emission Spectroscopy (BES)
X-ray Crystal Spectrometer
Soft X-ray Spectrometer
X-ray Pinhole Camera
X-ray Pulse Height Analysis
Multi-channel Neutron Collimator
Neutron Fluctuation Detectors
Charged Fusion Products
Charge Exchange Neutral Analyzer
Diagnostic Neutral Beam	Moveable Edge Probes
Divertor Thomson Scattering	

3.3.1.3  Structural and Cryogenic Criteria

TPX tokamak systems shall be designed in accordance with the TPX Structural and Cryogenic Design Criteria document.

3.3.1.4  Corrosion Prevention and Control

Materials, processes, and protective surface treatments or finishes shall be provided to ensure that equipment capability during its service life is not degraded due to corrosion.  Where possible, contact between dissimilar metals shall be avoided.

3.3.1.5  Neutral Beam Armor Materials

Carbon-based materials shall be used for the neutral beam armor. [GRD §1.3.6]

3.3.1.6  Divertor Materials

	a) The plasma-facing surfaces of the divertor assembly shall be made of carbon-based materials. [GRD §1.3.4.2]

	b) The minimum as-manufactured thickness of the graphite armor shall be 1.0cm between the plasma facing surface and the cooling tube interface. [GRD §1.3.4.2]

	c) The maximum divertor surface temperature shall not exceed 1400ºC. [GRD §1.3.4.2]

	d) The TPX facility shall be capable of being modified to accommodate alternate materials for plasma-facing surfaces including beryllium, tungsten, and molybdenum. [GRD §1.3.4.2]

3.3.1.7  Limiter Materials

	a) The plasma-facing surfaces of the limiter assemblies shall be made of carbon-based materials. [GRD §1.3.5.2]

	b) Maximum limiter surface temperatures shall not exceed 1200ºC. [GRD §1.3.5.2]

	c) For toroidally continuous limiters, the maximum toroidally averaged surface temperature shall not exceed 1000ºC. [GRD §1.3.5.2]

	d) The TPX facility shall be capable of being modified to accommodate alternate materials for plasma-facing surfaces including beryllium, tungsten, and molybdenum. [GRD §1.3.5.2]

3.3.1.8  Activation

Materials to be used in the design and construction of the system shall be such that waste packages generated during the disposal of the system at the end of its service life shall exceed Class A low-level waste limits as defined in existing 10CFR61 regulations.

3.3.2  Electromagnetic Radiation (EMR)

3.3.2.1  Electrical Referencing Requirements

	a)  Electrical reference.  All conductive structures and other conductive elements which are not part of functional electrical circuits, but which have any electrical purpose (such as attenuation of electromagnetic environments, etc.) shall be bonded together in accordance with the electrical requirements of 3.3.2.2 to form an electrical reference.  The electrical reference shall not be used for the conduction of functional current except that the shields of coaxial cables (being used as coaxial electromagnetic transmission media) may be incorporated as part of the electrical reference.

	b)  Reference connection.  Only one physical point in each electrical circuit shall be connected to the electrical reference.  The connection to the electrical reference shall be made at the physical point of the circuit which provides the greatest degree of electromagnetic energy control, which shall be capable of withstanding the maximum fault current without degradation and shall conform to the impedance requirements of 3.3.2.2.c between the circuit and the electrical reference.

	c)  Circuits to reference isolation.  All points of each circuit shall be isolated from the reference by a minimum resistance of 1 mega-ohm when the connection to the reference is opened, except for those circuits where terminal protection devices are used.

3.3.2.2  Electrical bonding

	a)  Bonding straps.  Bonding straps shall not be used except where mechanical contact cannot be physically accomplished.  the requirements for bonding straps and their characteristics shall be approved by the procuring activity prior to incorporation of bonding straps in the design.

	b)  Conductive elements in non-electrical application.  Where conductive materials are used in non-critical applications (i.e., where non-conductive materials could be used with no electrical impact on the system operation under any specified conditions), the conductive element shall have a mechanically secure connection to the electrical reference.  This connection shall have a DC resistance of less than one ohm and shall not be degraded beyond that value due to the maximum current caused by any specified environmental condition.

	c)  All other applications.  Conductive elements used in all other applications shall be in accordance with the following:

1.	Surface contact.  Electrical bonds between conductive parts shall be accomplished by conductive surface contact over entire areas which are held in mechanical contact.
	
2.	Resistance limits.  The maximum resistance of any electrical bond between any two conductive elements shall not exceed 2.5 milliohms where potential fault currents do not exceed 35 amperes.  Where potential fault currents are in excess of 35 amperes, the resistance of a single electrical bond shall not exceed 0.075/Isc  ohms, where Isc ohms is the worst case fault current through the bond in amperes.
	
3.	Impedance limits.  The maximum impedance of any single electrical bond shall not exceed a value increasing log-linearly from 3.5 milliohms at 1 kHz to 1.0 ohm at 50 MHz.
	
4.	Electromagnetic environment (EME) gaskets.  EME gaskets shall enhance metal-to-metal contact and shall be electrically continuous around the perimeter to be bonded.  The use of gaskets shall not degrade the maximum impedance values specified herein.

3.3.2.3  Shielding

3.3.2.3.1  Equipment cases

Equipment cases shall provide 80 dB (TBR) shielding effectiveness for electromagnetic radiation from 100 kHz (TBR) to 100 MHz (TBR) with a continuous conductive path for RF current over the entire surface area and the electrical reference.

3.3.2.3.2  Shield termination

All electromagnetic shields shall be circumferentially bonded to connector backshells and in turn, through the connectors to the equipment cases.  Individual internal shields covering single conductors, twisted pairs, triplets or quads or wires in the cable bundles shall be co-terminated with the cable shield.

3.3.2.3.3  Cable Shield Effectiveness

Shields on all cables shall provide a minimum shielding effectiveness of 40 dB (TBR) over a frequency range of 10 kHz (TBR) to 40 GHz (TBR).

3.3.2.4  Electromagnetic Environment

TBD.

3.3.2.5  EMI Characteristics

3.3.2.5.1  Conductors Exiting the Tokamak

Conductors that may couple to the internal tokamak RF heating field shall be filtered to attenuate conducted RF energy by 150 dB.  Shielding shall be used to prevent RF from radiating from the conductor between its exit from the tokamak and the filter.

3.3.2.5.2  Tokamak Ports Open to RF Heating Fields

RF radiation from ports shall be attenuated according to the limits specified by the PPPL ESHD 5008, Section 4, RF Field Safety, compared to fields at the internal tokamak wall.  Attenuation may be accomplished by port throat geometry (waveguide beyond cutoff) and/or shielding.

3.3.2.5.3  Diagnostics Equipment RF Tight Enclosures, Racks, and Cabling
 
	a)  The AC  power supplied to Diagnostic racks shall be EMI filtered.

	b)  Signal level connections between different diagnostics shall be fiber optic when practical.  If conductors are used, they shall be ground decoupled to preserve single point grounding.

3.3.3  Nameplates and Product Marking

3.3.3.1  Labels

Equipment and any parts of that equipment to be used by personnel shall be identified with appropriate labels.  Labels shall indicated clearly and concisely the function and purpose of the item being labeled.  Hierarchical labeling shall be used to facilitate component location on control panels.  The terminology used for equipment, procedures, and training materials shall be the same for each case.  Label design shall be consistent to promote simplicity and avoid clutter.  The use of abbreviations and acronyms shall be minimized.  Permanent labels shall be attached to the specific component or equipment in such a manner that environmental conditions or usage by personnel will not remove or destroy the label.  Temporary labels shall be used only when necessary and shall not obscure other information or equipment.  If a temporary label is to designate a device that is out of service, the label shall be applied so that it prevents the use of that device.  Labeling shall be legible and conform to human visual capabilities and limitations in regard to physical characteristics.  NUREG 0700, Section 6.6, and MIL-STD-1472C, Section 5.5, shall be used as a guide.

3.3.3.2  Identifying Devices

DOE Order 6430.1A, Section 1040, shall be used as a guide where identifying devices are required for buildings and facilities, including site and street facilities.  

3.3.4  Workmanship

During TPX fabrication and finishing, particular attention shall be given to freedom from blemishes, defects, burrs, and sharp edges; accuracy of dimensioning radii of weld fillets; making of parts; thoroughness of cleaning; quality of brazing, welding, riveting, painting, and wiring; alignment of parts; and tightness and torquing of fasteners.

3.3.5  Interchangeability

Design tolerances shall permit parts and assemblies of the same part number to be used as replacement parts without degrading the specified performance of the parent item.

3.3.6  Environmental, Safety, and Health (ES&H) Requirements

3.3.6.1  General Safety

When utilized within its intended use and within the environments specified by paragraph 3.2.6, the safe operation, test, handling, maintenance and storage of the system hardware and software shall be provided.

3.3.6.2  Safety Hazards

The system shall not present any uncontrolled safety or health hazard to user personnel.  The system shall detect abnormal operating conditions and safeguard the TPX system and personnel.

3.3.6.2.1  Neutron and Gamma Shielding

Neutron and gamma shielding shall limit nuclear heating of magnets, biological shielding, and to limit activation of components outside the shield.

3.3.6.2.2  Radiation Monitoring

A radiation monitoring system shall provide real-time and passive tritium, gamma, and neutron monitoring.

3.3.6.2.3  Controlled Access System

A controlled access system (CAS) shall protect against inadvertent entry into the test cell when electrical, magnetic, mechanical, toxic, or radiation hazards exceed allowable limits.

3.3.6.2.4  Diborane Gas Exposure

Monitors, alarms, and  a shutdown system shall prevent exposure to diborane gas.

3.3.6.3  Personnel Safety

The system shall meet all applicable OSHA requirements in accordance with 29CFR1910.  The system shall limit personnel exposure to hazardous materials to below their OSHA permissible exposure limit (PEL).

3.3.6.4  Flammability

The use of flammable materials shall be minimized.  Components containing flammable materials, fluids or gases shall be designed to minimize the possibility of leaks and spills.

3.3.6.5  Fire Suppression

A fire suppression system shall be provided for the TPX system which meets the requirements of DOE 5480.7 and PPPL ESHD-5008.

3.3.6.6  Hazardous Materials

Radioactive and hazardous waste shall be handled in accordance with federal, state, and local standards.

3.3.6.6.1  Activated Air Emissions

The TPX system shall provide controlled release of activated air to the environment and minimize spread of contamination to the facility.

3.3.6.6.2  Hazardous Liquid Containment

A facility drainage and collection system shall provide the capability to collect and store potential contaminated liquids

3.3.6.7  Electrical Safety

Electrical apparatus and systems shall be designed so that two simultaneous failures of high voltage (>600 V) barriers or a single failure of a low voltage barrier would have to occur to endanger workers performing work processes.

3.3.6.8  Radiological Design Objectives

The system shall meet the radiological design objectives and regulatory limits specified in Table 3.3.6.8.

3.3.7  Human Engineering

Human factors technology shall be considered in the design, operation, and maintenance of the TPX system.  The criteria and requirements provided in this section are applicable to the design of the work environment and human-machine systems at TPX facilities.  These criteria shall apply to new construction and to retrofitting of existing facilities.  These criteria shall be considered for upgrading existing facilities where cost-benefit or risk-tradeoff analyses indicate justification for such expenditures.  Human factors engineering considerations shall be included during the conceptual, preliminary, and design phases of the TPX system and shall follow the guidelines of DOE 6430.1A, Section 1300-12, and MIL-STD-1472.

3.3.7.1  Anthropometry 

Equipment that is to be used by personnel shall be designed or selected to accommodate the fifth to ninety-fifth percentile of the user population for stand-up and sit-down consoles and other work stations, for accessibility of equipment and instrumentation, for furniture and equipment layout, and for traffic flow in accordance with MIL-STD-1472C.

3.3.7.2  Human Environments

3.3.7.2.1  Temperature and Humidity

Temperature and humidity for human environments shall be maintained within limits recommended in NUREG 0700, Section 6.1, and UCRL 15673, Section 3.2.4.5.

3.3.7.2.2  Ventilation:
	
DOE 6430.1A, Section 1550-1.5, shall be used as a guide for HVAC system design.

3.3.7.2.3  Lighting

Adequate light levels shall be provided to meet control room illumination levels, luminance ratios, reflectance levels and further lighting considerations recommended in DOE 6430.1A, Section 1655, Interior lighting, and NUREG 0700, Section 6.1.  Glare and shadowing shall be avoided.

Table 3.3.6.8  Radiological Design Objectives

	P, Probability	Public Exposure1	Occupational Exposure	

Condition	Of Occurrence 
In A Year	Regulatory
Limit
(rem per yr)	Design
Objective
(rem per yr)	Regulatory
Limit
(rem per yr)	Design
Objective
(rem per yr)	
Routine Operation2	Normal Operations	P≥1	0.1 total
0.01 airborne3
0.004 drinking water	0.01 total	5	1	
	Anticipated Events	1>P≥10-2	0.5 total (including 
normal operation)	0.05 per
event			
Accidents4	Unlikely Events	10-2>P≥10-4	2.5	0.5	Note5	Note6	
	Extremely Unlikely Events	10-4>P≥10-6	25	57	Note8	Note9	
	Incredible Events	P<10-6	NA	NA	NA	NA	
Notes:	1Evaluated at the PPPL site boundary.
2Dose equivalent to an individual from routine operations (rem per year unless otherwise indicated)
3Compliance with this limit is to be determined by calculating the highest effective dose equivalent to any member of the public at any offsite point where there is a residence, school, business, or office.
4Dose equivalent to an individual from an accidental release (rem per event)
5Refer to PPPL ESHD 5008, Section 10, Chapter 12, for emergency personnel exposure limits.
6Refer to PPPL ESHD 5008, Section 10, Chapter 12, for emergency personnel exposure limits.
7For design basis accidents (DBAs), i.e., postulated accidents or natural forces and resulting conditions for which the confinement structure, systems. components, and equipment must meet their functional goals, the design objective is 0.5 rem.
8Refer to PPPL ESHD, Section 10, Chapter 12, for emergency personnel exposure limits.
9Refer to PPPL ESHD, Section 10, Chapter 12, for emergency personnel exposure limits.

3.3.7.2.4  Emergency Lighting

Emergency lighting systems shall be provided as required by NFPA 101.  A control room emergency lighting system shall be automatically activated and immediately available for (TBD) hours on failure of the normal lighting system.  The emergency lighting system for vital areas shall be an electrically independent system that is not degraded by failure of the normal lighting system.  Control room emergency lighting levels shall be in accordance with NUREG 0700, Section 6.1.5.4.

3.3.7.2.5  Noise

Acoustic design shall meet the limits of DOE 5480.10.  For further noise level and protection considerations, see NUREG 0700, Section 6, and UCRL 15673, Section 3.2.4.2.

3.3.7.2.6  Vibration

Vibration environments shall be reduced to the level of UCRL 15673, section 3.2.4.3, to the extent practical.

3.3.7.3  Component Arrangement

The arrangement of controls and displays on a control panel shall promote efficient use of task-related components, rapid location of any given component, and maximum operator awareness of plant conditions.  EPRI NP-3659, Chapter 4, and NUREG 0700, Sections 6.8 and 6.9, shall be used as a guide for component arrangement.

3.3.7.4  Protective Equipment

	a)  Personnel who work in a hazardous environment or who may be temporarily exposed to such hazards shall have convenient access to the appropriate protective equipment and garments.

	b)  Provisions shall be made for access, storage, and maintenance of protective equipment.

	c)  Personal protection equipment shall be compatible with the body sizes of personnel performing their tasks.  There shall be sufficient quantity of this equipment in the proper sizes for the required number of users.  There shall be provisions for an adequate supply of personal protective equipment expendables.  NUREG 0700, Section 6.1.4 shall be used as a guide.

	d)  The design or selection of protective equipment shall be such that it minimizes the impairment of operational and maintenance performance.

3.3.7.5  Display Devices

	a)  Displays shall provide only the information about system status and parameter values that is needed to meet task requirements in normal, abnormal and emergency situations.  Status, rather than demand information, shall be displayed for important parameters.  Displays shall indicate whether they reflect demand or actual status.

	b)  Each display shall be formatted and designed to ensure that both the display and display content are readable, understandable, and accessible.  NUREG 0700, Section 6.5, and MIL-STD-1472C, Section 5.2 shall be used as a guide for display design variables.

	c)  Failure of a display of any type shall be easily recognized and shall not affect equipment or system performance.

	d)  Where CRTs are used, rapid, error-free access to the information required for the task shall be accomplished by ensuring that system response to any query is less than 2 seconds and that user feedback to control action is less than 0.2 seconds or faster wherever possible.  NUREG CR-2496 shall be used as a guide.

3.3.7.6  System Controls

3.3.7.6.1  Operator Controls

A control panel operator shall be able to rapidly locate each component on a panel.  control panels shall be designed to reduce operator information overload.  EPRI NP 3659, Chapter 4, NUREG 0700, Sections 6.1, 6.3, 6.7 and 6.9, and Van Cott and Kincade, Human Engineering Guide to Equipment Design, Chapter 9, shall be used as a guide.

3.3.7.6.2  Component Controls

	a)  Each control device shall provide the appropriate control capability, range, and sensitivity for necessary control settings and manipulations.  Control components shall be durable, compatible with nontypical apparel where required, and not prone to accidental activation.

	b)  Selection of controls shall consider the use of coding methods including location, size, shape, and color.  NUREG 0700, Section 6.4, shall be used as a guide.

	c)  NUREG 0700, Section 6.4, MIL-STD-1472C, Section 5.4, and Van Cott and Kincade, Chapter 8, shall be used as a guide for criteria to be applied to common controls such as rotary controls, toggle switches, push buttons, rocker switches, and linear switches.

3.3.7.7  Warning and Annunciator Systems

	a)  An effective warning system shall be provided to alert personnel to a problem or abnormal condition and shall provide sufficient time to respond appropriately to the problem.  MIL-STD-1472C, Section 5.3, shall be use in design of warnings.  NUREG 0700, Section 6.3, shall be used in design of control room annunciators.  NUREG 0700, Section 6.2, shall be used in design of auditory signals.

	b)  Analyses shall be performed to determine whether both auditory and visual stimuli shall be used or just one of them.  Van Cott and Kincade, Chapter 4, shall be used as a guide.

	c)  Each stimulus shall be easily distinguishable from other stimuli in the same modality but it shall not be a distraction.  If an alarm can be one of many similar alarms that may occur simultaneously, it shall be easy to locate.

	d)  Any specific stimulus shall have only one meaning to either designate one problem or be a signal to look at a particular place to define the alarm further.  When there are many annunciator alarms, priority coding such as “first in/out” shall be used to assist in determining message significance.  False alarms and nuisance alarms shall be removed.  Set point determination shall allow sufficient response time to the operator.

	e)  Provision shall be made for active acknowledgment and for silencing of auditory alarms after they have been acknowledged.

	f)  Provision shall be made for maintaining personnel awareness of alarm conditions until they have been corrected or “cleared.”  Clearing of the alarm shall require a positive response from the assigned personnel.

	g)  Visual alarm tiles shall be grouped by function or system within panels having horizontal and vertical alphanumeric labeling for ready coordinate designation of individual tiles.  Legends shall be unambiguous and address specific conditions.

	h)  It shall be possible to test the warning system periodically.

3.3.7.8  Communications Systems

	a)  A communication system shall allow the users to transmit and receive information accurately and conveniently with minimum distraction from the user’s other tasks.  The system shall have provisions for periodic maintenance tests, instructions for the use of each system used, and procedures for handling emergency communications where applicable.

	b)  Public announcing systems shall have loudspeakers located to eliminate dead spots.  Headsets for sound-powered telephones shall leave the hands free.  MIL-STD-1472C, Van Cott and Kincade, Chapter 5, and NUREG 0700, Section 6.2 shall be used as guides.

3.3.8  Nuclear Control

N/A.

3.3.9  System Security

The system shall provided security features with the capability to protect against unauthorized access and use of the TPX system.

3.3.10  Government Furnished Property Usage

Government Furnished Equipment (GFE), Government Furnished Information (GFI), and Government Furnished Software (GFS) listed in Table 3.3.10 provided by the government shall be incorporated into the TPX system design.  

Table 3.3.10 Government Furnished Equipment, Information, and Software

Item No.	Nomenclature	Specification No.	Stock/Part No.	Comments	
	(TBD)				

					

3.3.11  Computer Resource Reserve Capacity

The design of the computer equipment shall include a 100% (TBR) margin for volatile and non-volatile memory.  The throughput capacity of each processor shall be (TBD).

3.4  Documentation

N/A

3.5  Logistics

3.5.1  Maintenance

The system shall be maintained using, to the extent possible, standard/common tools and existing multi-purpose test equipment.  Use of new/special tools and the number of standard/common tools shall be minimized through maximum commonality of fasteners, clamps, adapters, and connectors.

3.5.1.1  Test Cell Maintenance

3.5.1.1.1  Hands-on Maintenance

Hands-on maintenance shall be provided for during an initial two year (TBR) period during which low activation of the Test Cell is expected.  Extensive shielding between the vacuum vessel and the toroidal magnets as well as around all ducts and ports shall be provided to protect maintenance personnel.  Hands-on maintenance shall be limited to removal and replacement of component parts.

3.5.1.1.2  Remote Maintenance

Remote maintenance shall include the removal and replacement of component parts within the Vacuum Vessel.  Design of the robotics maintenance system shall consider standardized/common rails, manipulators, drive mechanisms, visual components, and control systems as well as fasteners, clamps, adapters, and connectors for use inside the vacuum vessel.

3.5.2  Supply

Spare components shall be stored at TBD.  TPX fuel shall be received and stored at TBD.  The TPX system shall use the existing PPPL supply system (TBR).

3.5.3  Facilities

Maximum use shall be made of the existing facilities and equipment at the TPX site.  Modifications and new facilities shall be constructed only where existing facilities are not adequate to house, store, maintain, operate, or test the TPX system and shall be designed in accordance the applicable requirements of DOE 6430.1A.

3.6  Personnel and Training

3.6.1  Personnel

Selection and qualification of personnel involved in the operation, maintenance, and technical support of TPX Test Cell and site facilities shall be in accordance with DOE 5480.20, Chapter IV.  Qualification and certification procedures for site personnel shall be documented to define those necessary to meet TPX performance requirements.

3.6.2  Training

System training shall be accomplished via TBD.  Provisions shall be made to train operators and maintainers of the TPX system.  Equipment shall be designed to accommodate initial and recurring operations and maintenance training in an operational and/or training environment.

3.7  Characteristics of Subordinate Elements

3.7.1  Plasma Facing Components (PFC)

3.7.1.1  Resistive Breaks

The conducting structure shall include resistive breaks to provide sufficient toroidal resistance for penetration of the startup voltage. [GRD §1.8.4]  Specifically, the minimum toroidal resistance of the plasma facing components shall not be less than TBD W.

3.7.1.2  Component Power Handling Requirements

3.7.1.2.1  Divertor Power Handling

	a) The inboard and outboard divertor targets shall be designed for handling peak heat fluxes of 7.5MW/m2 under steady state conditions. [GRD §1.3.4.3]

	b) The private region baffle shall be designed to handle peak heat fluxes of 4 MW/m2 under steady state conditions. [GRD §1.3.4.3]

3.7.1.2.2  Inner Toroidal Limiter Power Handling

The inboard limiters shall be designed to accommodate local heat loads due to NB shine-through, radiation, and plasma startup. [GRD §1.3.5.3]

3.7.1.2.3  Outer Toroidal Limiter Power Handling

The outboard toroidal limiters shall be designed to accommodate local heat loads due to ripple-trapped particles, radiation, and plasma startup. [GRD §1.3.5.3]

3.7.1.2.4  Neutral Beam Armor Power Handling

Armor to protect the vacuum vessel and its appendages from damage due to steady-state neutral beam shine-through attendant with a line-averaged plasma density of 0.3x1020/m3, and due to inadvertent unattenuated neutral beam loads for 50 ms at full power, shall be provided. [GRD §1.3.6]

3.7.1.2.5  Poloidal Limiters Power Handling

The poloidal limiters shall be designed to handle peak heat fluxes of TBD MW/m2 under steady state conditions.

3.7.1.2.6  Other Line-of-Sight Components Power Handling

The other line-of-sight components specified in Table 3.7.1.2.6 shall be designed to handle peak heat fluxes of TBD MW/m2 under steady state conditions.

Table 3.7.1.2.6  Other line-of-Sight Components Power Handling

Component	Peak Heat Flux (MW/m2)	
TBD	TBD	

		

3.7.1.3  Divertor Configuration

3.7.1.3.1  Peak Heat Load Reduction

The divertor configuration shall accommodate a gaseous or radiative target designed to be capable of reducing peak heat loads on the divertor targets, and shall include:

	a)  a slot geometry with a baffle in the private region and high heat flux divertor targets,

	b)  auxiliary baffles to direct the neutralized plasma exhaust into the pump duct and block the flow of gas and impurities to the main plasma, and

	c)  diagnostic viewing access to the main plasma and to the divertor itself. [GRD §1.3.4.1]

3.7.1.3.2  High Heat Flux Region Geometry

High heat flux regions on the divertor targets shall be provided with geometry per the reference scenario Section 3.2.1.4.3.3.1. [GRD §1.3.4.1]

3.7.1.3.3  Maximum Auxiliary Baffle Leak Rate

The maximum allowable leak rate through the auxiliary baffles and into the SOL of the plasma is 8,500 l/s. [GRD §1.3.4.1]

3.7.1.3.4  Divertor Assembly Reconfiguration

Flexibility to reconfigure the divertor assemblies shall be provided. [GRD §1.3.4.1]

3.7.1.4  Limiter Configuration

	a) Toroidal and poloidal limiters shall be provided outboard of the plasma for startup and to protect the outboard passive structure and equipment in the port region from energetic particle fluxes during steady state operation and disruptions. [GRD §1.3.5.1]

	b) Two outboard toroidal limiters shall be provided which intersect the two outboard toroidal limiter horizon points and remain outside the +2cm SOL envelope as prescribed in the scrape-off layer envelopes Section 3.2.1.4.4.1. [GRD §1.3.5.1]

	c) The outboard poloidal limiter horizon shall conform to the geometry of the Faraday Shield on the ICH/FWCD launcher. [GRD §1.3.5.1]

	d) Toroidal limiters shall be provided inboard of the plasma for startup and to protect the inboard passive structure and equipment located inboard of the plasma from energetic particle fluxes during steady state operation and disruptions. [GRD §1.3.5.1]

	e) The inboard toroidal limiter horizon shall intercept the midplane at a radius of 1.65m. [GRD §1.3.5.1]

	f) Protective armor shall be provided to protect the outboard passive structure and components between the passive structure and vacuum vessel wall from energetic particle losses due to field ripple. [GRD §1.3.5.1]

3.7.2  Vacuum Vessel (VV) System

3.7.2.1  Base Pressure

The vacuum vessel assembly shall be capable of reaching a base partial pressure of 1x10-7 torr for fuel gases (Z ≤ 2) and a base partial pressure of  ≤ 1x10-9 torr for impurity gases (Z > 2) at 65ºC.

3.7.2.2  Leak Rate

The maximum total allowable leak rate for the vacuum vessel assembly is TBD torr-l/s with 150±TBDºC water in the vessel jacket.

3.7.2.3  Alignment and Operational Stability

	a)  The vacuum vessel shall provide the divertors with a toroidal alignment accuracy of ±5 mm relative to the magnetic axis of the machine during operation.

	b)  The vacuum vessel shall provide PFC’s other than the divertors with a toroidal alignment accuracy of ±1 mm relative to the magnetic axis of the machine during operation.

	c)  The vacuum vessel shall maintain a toroidal alignment accuracy of ±TBD mm relative to the magnetic axis of the machine under normal operating conditions.

3.7.2.4  Toroidal Resistance

The toroidal resistance of the vacuum vessel assembly shall be at least TBD Ohms to provide sufficient resistance for startup.

3.7.3  Toroidal Field (TF) System

	a) The TF System shall feature of 16 identical TF coils spaced at 22.5º intervals.

	b) Each TF coil shall be fabricated of superconducting Nb3Sn cable-in-conduit-conductor (CICC). The coil shall consist of 12 pancakes of 7 turns each, for a total of 84 turns.

	c) TF coils shall be fabricated in eight 2-coil modules.  Each 2-coil module shall lie completely within the envelope defined by TPX Drawing E-9413102 Sheets 1-3.

	d) 2-coil modules shall be assembled into 4-coil quadrants prior to installation.  Each 4-coil quadrant shall lie completely within the envelope defined by TPX Drawing E-9413103 Sheets 1-2.

	e) The completed TF assembly will have 2 electrical interleaves.  The routing of the lead pairs shall conform with TPX Drawing E-13001 Sheet 1.

	f) The TF conducting structure shall include insulating breaks to facilitate penetration of the startup voltage and minimize eddy current heating in the TF structure.

3.7.4  Poloidal Field (PF) System

	a) The PF system shall consist of 7 upper and lower coil pairs.  Each coil pair shall be interchangeable.  The innermost 4 coil pairs shall be assembled in a central solenoid (CS) assembly.

	b) The PF system shall be designed such that at operating temperature, the PF coils are symmetrically located about the TF horizontal midplane, defined as the plane with the maximum clear horizontal bore.

	c) At room temperature (nominally 20ºC), PF winding packs (defined by the outside of the ground wrap) shall lie completely within the envelopes defined in TPX Drawing E-14002 Sheet 1.

	d) PF coil leads shall be routed in accordance with TPX Drawing E-14003 Sheets 1-3.

	e) In order to provide sufficient toroidal resistance for penetration of the startup voltage and to minimize eddy current heating of the PF coil assemblies, the minimum toroidal resistance of the PF coil assemblies (excluding the conductor circuits) shall not be less than TBD Ohms.

3.7.5  Cryostat

TBD.

3.7.6  Tokamak Support Structure

The tokamak support structure shall include insulating breaks to facilitate penetration of the startup voltage and minimize eddy current heating in the tokamak support structure.

3.7.7  Tokamak Assembly

TBD.

3.7.8  Tokamak Shielding

TBD.

3.7.9  FEC and FPPC Coil Systems

TBD.

3.7.9.1  FEC Coil System

	a) The FEC coil system shall feature 12 coils mounted on the TF assembly -- 4 on top, 4 on the bottom, and 4 on the outboardside.

	b) FEC coils mounted on the top of the TF assembly shall be identical.  FEC coils mounted on the bottom of the TF assembly shall also be identical.  Likewise, FEC coils mounted on the top of the TF assembly shall also be identical.

	c) FEC coils shall be superconducting.

	d) Each FEC coil shall lie completely within the envelope defined by TPX Drawing TBD.

	e) Six circuits shall be provided for field error correction.  Diametrically opposed coils shall be connected in anti-series to minimize the net mutual inductance between FEC coils and PF coils and between the FEC coils and the FPPC coils.

	f) The routing of FEC coil leads shall conform to TPX Drawing TBD.

3.7.9.2  FPPC Coil System

3.7.10  Neutral Beam System

Description.

Neutral beams are required to provide ion heating, bulk current drive, and core fueling; sustain plasma rotation; and support diagnostic requirements. [GRD §1.4.1]

3.7.10.1  8MW Neutral Beam Power

The device and facility shall initially be configured to provide 8MW of neutral beam power to the plasma (one TFTR beamline modified for 1000s pulse lengths aimed in the direction of positive plasma current, i.e. co-directed). [GRD §1.4.1]

3.7.10.2  Beamline Orientation

The beamlines shall be oriented with a tangency radius for the center beam of 2.00±0.05m. [GRD §1.4.1]

3.7.11  Electron Cyclotron Heating and Current Drive

Description.

The ability to accommodate the addition of ECH/ECCD is required to provide a backup approach for start-up assist, discharge cleaning, electron heating, and localized current profile control. [GRD §1.4.4]

Performance Requirements.

TBD.

3.7.12  Ion Cyclotron Heating and Fast Wave Current Drive

Description.

ICH/FWCD is required to provide electron heating and centrally-peaked current drive. [GRD §1.4.2]

3.7.12.1  6 MW ICH/FWCD Power

	a)  The device and facility shall initially be configured to provide 6 MW of ICH/FWCD power to the plasma. [GRD §1.4.2]

	b)  The ICH/FWCD power shall initially be coupled to the plasma through one 6-strap launcher. [GRD §1.4.2]

3.7.12.2  ICH/FWCD Power at a Single Frequency

The ICH/FWCD system shall be capable of providing ICH/FWCD at a single frequency in the range of 40‑80 MHz. [GRD §1.4.2]

3.7.12.3  ICH/FWCD Power at Three Frequencies

	a)  The system shall be capable of operating at any of three frequencies in the range of 40‑80 MHz (by changing tuning and matching elements outside the plasma vacuum boundary) [GRD §1.4.2]

	b) The tuning and matching elements required for operation at all three frequencies in 3.7.12.3.a) above shall be provided for initial operation. [GRD §1.4.2]

3.7.12.4  Use of Faraday Shield

	a)  A Faraday shield shall be provided between the launcher and plasma. [GRD §1.4.2]

	b) At operating temperature, the front surface of the Faraday shield shall conform (±2mm) to the surface of a circular toroid located on the midplane with major radius 1.832 m and minor radius 0.938 m within 0.4m of the midplane.  This surface bounds the family of +2cm flux surfaces over the required range of flexibility in b-li space. [GRD §1.4.2]

	c) The capability to move the ICH/FWCD launcher out 0.1m from the innermost position specified in 3.7.12.4.b above shall be provided. [GRD §1.4.2]

3.7.13  Lower Hybrid Heating and Current Drive (LHH/LHCD)

Description.

LHH/LHCD is required to provide off-axis current profile control, efficient bulk current drive at low plasma temperatures, and electron heating. [GRD §1.4.3]

3.7.13.1  3MW LHH/LHCD Power

The device and facility shall initially be configured to provide 3 MW of LHH/LHCD power to the plasma at 3.7 GHz through one horizontal port. [GRD §1.4.3]

3.7.13.2  Dynamic Variance of Wave Number Spectrum

The LHH system shall provide capability to dynamically vary the wave number spectrum in order to support flexible off-axis current profile control. [GRD §1.4.3]

3.7.13.3  Surface Configuration of LH Launcher

The front surface of the LH launcher shall conform to the surface of a circular toroid located on the midplane with major radius 1.817 m and minor radius 0.953 m over its length.  This location corresponds to the contour of the outboard poloidal limiter horizon. [GRD §1.4.3]

3.7.13.4  Movement of LH Launcher

The capability to move the LH launcher during a pulse over a distance of 5cm at a rate of 0.5cm/s shall be provided. [GRD §1.4.3]

3.7.14  Fuel Storage and Delivery Systems

TBD.

3.7.15  Pellet Injection System

TBD.

3.7.16  Radiation Monitoring and Tritium Cleanup Systems

TBD.

3.7.17  Vacuum Pumping Systems

3.7.17.1  Vacuum Pumping Speed and Throughput

3.7.17.1.1  Neutral Pressure Vacuum Pumping Rates

The TPX facility shall be designed to provide a vacuum pumping rate of 50 torr-l/s with a neutral pressure of 0.8 mtorr at the entrance to the vacuum pump duct. [GRD §1.3.7]

3.7.17.1.2  Maximum Vacuum Pumping Rates

The TPX facility shall be designed for maximum vacuum pumping rates of  torr-l/s when operated at the pulse repetition rates specified in Section 3.2.1.4.7.2 and torr-l/s when operated at lower pulse repetition rates. [GRD §1.3.7]

3.7.17.1.3  Minimum Vacuum Pumping Speeds

The TPX facility shall provide a minimum vacuum pumping speed of 65,000 l/sec. [GRD §1.3.7]

3.7.17.1.4  Vacuum Pumping Speed Control

A variable aperture on the vacuum pumping ducts shall be provided to control the vacuum pumping speed. [GRD §1.3.7]

3.7.18  Power Systems

TBD.

3.7.19  Maintenance Systems

TBD.

3.7.20  Central I&C Systems

TBD.

3.7.21  Plasma Diagnostics

3.7.21.1  Plasma Control Diagnostics

	a) An array of magnetic diagnostics shall be provided to measure the plasma and vacuum vessel currents, the radial and vertical plasma position, the outboard divertor strike point, and the plasma shape with time resolution and accuracy sufficient to satisfy the associated control and operational requirements in the Plasma Startup Section 3.2.1.4.2 and the Equilibrium Control Section 3.2.1.4.3.3.3. [GRD §1.11]

	b) Profiles of the plasma current density and the plasma pressure shall be provided to support the TPX advanced tokamak mission through active control of the plasma profiles. [GRD §1.11]

	c) Magnetic measurements of MHD and locked mode activity shall be provided in support of disruption handling requirements in Section 3.2.1.4.5. [GRD §1.11]

	d) The line-averaged density (<n> ≤ 1.5x1020 m-3) shall be measured to provide feedback control of the plasma density. [GRD §1.11]

3.7.21.2  Confinement Diagnostics

	a) Core profiles of the electron density (neo ≤ 4x1020 m-3), electron temperature (Teo ≤ 25 keV), ion temperature (Tio ≤ 25 keV), average impurity concentration (Zeff ~ 1-5), and the radiated power shall be measured. [GRD §1.11]

	b) Measurements of the plasma poloidal beta (0.01<bp<5.0) and the low-Z and high-Z impurity concentrations shall be provided. [GRD §1.11]

	c) Internal and external fluctuations shall be measured over a range of frequencies adequate to encompass MHD activity and plasma instabilities. [GRD §1.11]

3.7.21.3  Divertor/Edge Plasma Diagnostics

	a) The divertor and limiter surface temperatures shall be measured from ~ 300 ºC to 3000 ºC with maximum coverage consistent with viewing access to provide operational information needed for wall conditioning, impurity control, and protection of plasma facing components. [GRD §1.11]

	b) Measurements of the electron density, ion/electron temperatures, neutral pressure, and the Ha and impurity line radiation in the SOL and divertor plasma region shall be provided. [GRD §1.11]

3.7.21.4  Fusion Yield Diagnostics

The total neutron source rate (G less than or equal to 1.5x1017 n/s) and the radial profile of the neutron source emission shall be provided, as well as measurements of the charged fusion products. [GRD §1.11]

3.7.21.5  Baseline Diagnostics

The device and facility shall include the baseline diagnostics shown in Table 3.7.21.5 below: [GRD §1.11.1]

Table 3.7.21.5  Baseline Diagnostics

Machine Diagnostics	Physics Diagnostics	Divertor/Edge Diagnostics	
Magnetic Loops
Hard X‑ray Detectors
Millimeter-wave Interferometer
UV Survey Spectrometer
Plasma/Infrared TV
Visible Survey Spectrometer
Residual Gas Analyzer
Torus Ion Gauges
Glow Discharge Probes
Inspection Illumination	Visible Filterscopes
Visible Bremsstrahlung
Charge Exchange Spectroscopy
Thomson Scattering
Motional Stark Effect (MSE)
Soft X‑ray Arrays
Epithermal Neutron Detectors
ECE Heterodyne Radiometer
Bolometer Arrays
Fixed Edge Probes	Divertor IR TV
Visible Ha TV
Foil Bolometers
Divertor Bolometer Arrays
Multichord Visible Spectrometer
Fast Neutral Pressure Gauges
Ha Monitors
Thermocouples	

3.7.22  Building, Modifications, and Site Improvements

TBD.

3.7.23  Cryogenic Systems

TBD.

3.7.24  Water Systems

Unless otherwise specified, the HCS shall meet the following requirements for the baseline system.  The HCS shall be capable of being upgraded to support the upgrades for pulse operation at 45 MW and for steady state operation.

3.7.24.1 50°C Cooling Water System

The HCS shall provide a 50°C water cooling loop capable of satisfying the performance requirements specified in Table 3.7.24.1.

Table 3.7.24.1  50°C Cooling Water System Performance Requirements

	Baseline	Pulse	Temperature	Flow	Pressure			
Supported Subsystem	Operation1	Load
(MW)	Inlet (°C)	Avg. Delta (°C)	Rate (gpm)	Min. Inlet (psig)	Max. Delta (psi)	Vol.
(gal)	Conduct.
(MOhm-cm)	
WBS 11 - PFCs	I
II-III	18
45	50
50	15.1
15.1	4512
11295	290
290	58
58	800
800	1
1	
WBS 18 - Tokamak Shielding	I
II-III	3.72
3.72	50
50	19.2
19.2	732
732	20
20	5
5	TBD
TBD	1
1	
WBS 19 - FPPC/FEC	I-II-III	1.98	50	30.0	250	100	65	TBD	1	
WBS 23 - ICH/FWCD
WBS 231 - ICH Antenna	I
II-III	0.365
0.365	50
50	4.5
7.2	305
350	100
150	26
30	TBD
TBD	1
1	
WBS 232 - Tuning & Matching	I
II-III	0.3
0.9	50
50	7.6
7.6	150
450	100
100	30
30	TBD
TBD	1
1	
WBS 24 - LHH/LHCD
WBS 241 - LH	I
II-III	0.32
0.79	50
50	12.1
12.0	100
250	100
100	90
90	TBD
TBD	1
1	
WBS 62 - Diagnostics	I
II-III	0.01
0.073	50
50	6.5
41.9	5.8
6.6	200
200	20
20	TBD
TBD	1
1	
TOTAL	I
II-III	24.7
53.1								
1  I=Pulse operation at 18 MW; II=Pulse operation at 45 MW; III=Steady state operation at 45 MW

3.7.24.2  Borated Water System

The HCS shall provide a 50°C borated water loop (using B-10 enrichment) to provide thermal neutron shielding to the vacuum vessel and penetrations.  The loop shall have a shielding equivalent of 110 grams/liter of boric acid and satisfy the performance requirements specified in Table 3.7.24.2.  This requirement is not dependent upon the mode of operation (baseline vs. state of upgraded system capability).

3.7.24.3  Bakeout System

	a)  The HCS shall support the bakeout process by heating the vacuum vessel shell and its internal components to a temperature of 350°C ± 25°C within a 48 hour time period and maintaining that temperature for an indefinite period of time.

	b)  The HCS shall be capable of cooling the vacuum vessel shell and its internal components to TBD°C ± TBD°C within TBD hours following the completion of bakeout activities.

Table 3.7.24.2  Borated Water System Performance Requirements

	Temperature	Flow	Pressure		
Supported Subsystem	Inlet (°C)	Avg. Delta (°C)	Rate (gpm)	Min. Inlet (psig)	Max. Delta (psi)	Volume
(gal)	
WBS 12 - Vacuum Vessel	50	-3	4	20	5	5300	
WBS 18 - Tokamak Shielding	50	0	2.33	20	5	3400	

3.7.24.4  Chilled Water System

The HCS shall provide a chilled water cooling loop capable of satisfying the performance requirements of Table 3.7.24.4.

Table 3.7.24.4  Chilled Water System Performance Requirements

	Baseline	Pulse	Temperature	Flow	Pressure			
Supported Subsystem	Operation1	Load
(MW)	Inlet (°C)	Avg. Delta (°C)	Rate (gpm)	Min. Inlet (psig)	Max. Delta (psi)	Vol.
(gal)	Conduct
(MOhm-cm)	
WBS 21 - NB Injection
Beam Line	I
II-III	25
75	<27
<27	11.8
11.8	8000
24000	150
150	90
90	TBD
TBD	1
1	
Ion Sources	I
II-III	2
6	<27
<27	15.1
15.1	500
1500	150
150	135
135	TBD
TBD	17
17	
WBS 23 - ICH/FWCD
WBS 234 - Transmitters	I
II-III	9
18	<27
<27	42.1
42.1	810
1620	120
120	87
87	TBD
TBD	1
1	
WBS 24 LHH/LHCD
WBS 243 (50%) -  Klystrons	I
II-III	5.66
11.3	<27
<27	39.0
38.9	550
1100	75
75	40
40	100
200	1
1	
WBS 4X - Power	I
II-III	3.3
3.3	<27
<27	4.2
4.2	3000
3000	TBD
TBD	TBD
TBD	TBD
TBD	1
1	
TOTAL	I
II-III	45.0
113.6								
1  I=Pulse operation at 18 MW; II=Pulse operation at 45 MW; III=Steady state operation at 45 MW

3.7.24.5  Demineralized Cooling Water System

The HCS shall provide a demineralized water cooling loop capable of meeting the performance requirements specified in Table 3.7.24.5.  This system shall be maintained at less than or equal to 35°C.

3.7.24.6  Heat Rejection System

The HCS shall utilize the C- and D-site cooling towers to reject the heat loads specified in Table 3.7.24.6.

3.7.24.7  Makeup Water System

The HCS shall provide a supply of de-ionized (resistivity greater than 1 MOhm-cm), deoxygenated (oxygen concentration less than 0.5 ppm), and filtered (100 percent removal of particles greater than 5 micrometers) water to support the start-up, operation, and maintenance of the TPX system.  This system shall be capable of satisfying a demand of 100 gpm for at least one hour of continuous use.

Table 3.7.24.5  Demineralized Cooling Water System Requirements

		Pulse	Temperature	Flow	Pressure			
Supported Subsystem	Baseline Operation1	Load
(MW)	Inlet (°C)	Avg. Delta (°C)	Rate (gpm)	Min. Inlet (psig)	Max. Delta (psi)	Vol.
(gal)	Conduct.
(MOhm-cm)	
WBS 21- Power Supplies	I
II-III	11
33	<35
<35	11.9
11.9	3500
10500	140
140	100
100	TBD
TBD	1
1	
WBS 233 - Transmission Lines	I
II-III	0.6
1.2	<35
<35	18.9
18.9	120
240	50
50	TBD
TBD	522
1044	1
1	
WBS 242 and 50 % of WBS 243 - All RF Components	I
II-III	1.22
2.44	<35
<35	19.6
19.6	235
470	75
75	50
50	5.2
10.4	1
1	
WBS 34 - Vacuum Pumping	I
II-III	0.254
0.254	<35
<35	26.4
26.4	36.4
26.4	75
75	10
10	<90
<90	1
1	
TOTAL	I
II-III	13.1
36.9								
1  I=Pulse operation at 18 MW; II=Pulse operation at 45 MW; III=Steady state operation at 45 MW

Table 3.7.24.6  Heat Rejection System Performance Requirements

		Pulse	Temperature	Flow	Pressure		
Supported Subsystem	Baseline Operation1	Load
(MW)	Inlet (°C)	Avg. Delta (°C)	Rate (gpm)	Min. Inlet (psig)	Max. Delta (psi)	Vol.
(gal)	
WBS 72 - Cryogenic Systems	I
II-III	5
15	<35
<35	5.9
5.9	3200
9600	110
110	50
50	TBD
TBD	
WBS 4X - Power Systems (MG Set)	I
II-III	3.5
3.5	<35
<35	6.0
6.0	2200
2200	TBD
TBD	TBD
TBD	TBD
TBD	
C&D Facility	I
II-III	6
6	<35
<35	6.0
6.0	3785
3785	TBD
TBD	TBD
TBD	TBD
TBD	
WBS 731 Secondary Cooling	I
II
III	5.5
11.8
53.1	<35
<35
<35	6.0
6.0
6.0	3458
7440
33515	TBD
TBD
TBD	TBD
TBD
TBD	TBD
TBD
TBD	
WBS 734 - Secondary Cooling	I
II
III	10.0
25.2
113.6	<35
<35
<35	6.0
6.0
6.0	6296
15909
71663	TBD
TBD
TBD	TBD
TBD
TBD	TBD
TBD
TBD	
WBS 735 - Secondary Cooling	I
II
III	2.9
8.2
36.9	<35
<35
<35	6.0
6.0
6.0	1831
5167
23274	TBD
TBD
TBD	TBD
TBD
TBD	TBD
TBD
TBD	
TOTAL	I
II
III	33
70
228							
1  I=Pulse operation at 18 MW; II=Pulse operation at 45 MW; III=Steady state operation at 45 MW

3.7.24.8  Gas Blanket and Vent System

The HCS shall provide a gas blanket and vent system capable of performing the following functions:

	a)  Provide low pressure (TBD psi) argon for inert gas blanketing of atmospheric or low pressure storage tanks and piping vent tanks.

	b)  Provide high pressure argon for maintaining base pressure (TBD psi) in the pressurized Tokamak Cooling System and to provide TBD psi argon to support the bakeout process (see paragraph 3.7.24.3).

	c)  Provide controlled tank and system venting and pressure regulation to support system fill and drainage to remove accumulating non-argon gas.

3.7.25  Test Cell Penetrations

TBD.

3.8  Precedence

N/A.

3.9  Qualification

N/A.

3.10  Standard Sample

N/A.

3.11  Preproduction Sample

N/A.

4.  QUALITY ASSURANCE PROVISIONS
4.1  General

This section identifies the methods to be used for verification of requirements in section 3 of this specification.  General definitions of basic verification methods are outlined.  System requirements will be allocated in part or total to lower-level TPX element specifications.  These allocations will be traced in the Compliance Allocation Matrix (CAM).  Verification and qualification of individual components will be conducted in accordance with individual specifications.  Verification of system requirements will require additional testing in operational or near-operational environments.  Detailed planning for verification of all system requirements will be documented in the TPX Test & Evaluation Plan (TEP).  The Test Planning Working Group (TPWG) process will involve representatives from all TPX team elements to identify and refine detailed system test requirements and resources and schedules. 

4.2  Responsibility For Inspection

Unless otherwise stated, contractors are responsible for the planning and performance of all inspection requirements including test, examination, demonstration and analysis that pertain to components and subsystems under their development.  Detailed allocation will be developed in the CAM, and the CAM will be used for final verification of system requirements.  Contractors will support system testing at operational facilities as derived by the TPWG process and in accordance with direction from the TPX project office.

4.3  Responsibility For Conformance

All items, components and subsystems shall meet the requirements of section 3 and 5 of this specification.  The inspections set forth in this specification shall become a part of the contractors’ overall quality program.

4.4  Inspection Verification Methods

Verification of qualification shall be by examination, demonstration, test or analysis.  Definition of examination, demonstration, test and analysis is as follows:

 	a)  Examination:  Examination is an element of inspection consisting of investigation, without the use of special laboratory appliances, procedures or supplies and services to determine conformance to those specified requirements which can be determined by such investigations.  Examination is generally non‑destructive and includes but is not limited to, simple physical manipulation, gauging and measurement, visual, auditory, olfactory, tactile, gustatory and other investigations.

	b)  Test:  Test is an element of inspection denoting the determination of the properties or elements of supplies or components thereof by technical means, including functional operation and the application of established principles and procedures.  The analysis of data derived from test is an integral part of the inspection element and shall not be confused with “Analysis” below.

	c)  Demonstration:  Demonstration is an element of inspection  that, although technically a variation of test, differs from “Test” above, by directness of approach in the verification of a requirement and is accomplished without the use of elaborate instrumentation or special equipment.  Thus, operation of a representative configuration item (CI) in or near its use environment would be defined as a demonstration rather than a test.

	d)  Analysis:  Analysis is an element of inspection in the form of a study resulting in data that is intended to verify a requirement when an examination, test, or demonstration cannot feasibly be employed to verify the requirement. Such data may be a compilation or interpretation of existing data, analysis, design solutions, lower-level inspection results.

4.5  Quality Conformance

This section establishes the specific evaluation criteria for verification of the system requirements in sections 3 and 5.  Each section 3 and 5 requirement is associated with a section 4 verification method. The cross-reference matrix included as Table 4.5 indicates the verification method required to verify conformance and references the applicable detailed verification requirements from paragraph 4.5.1, if any.  Detailed quality conformance requirements and constraints are listed below.  In general, all requirements shall be verified under operational or near-operational conditions as possible given test constraints.

Note:  The contents of the following paragraphs and Table 4.5 are intended to represent examples only and do not represent TPX Project coordinated requirements.

4.5.1  Detailed Quality Conformance Requirements 

4.5.1.1  Magnet Cooldown Timelines (ref. 3.2.1.3.2.1)

Superconducting magnet cooldown shall be tested in the operational facility using available refrigeration capacity of the MFTF-B.

4.5.1.2  Magnet Warmup Timeline (ref.  3.2.1.3.2.2)

Superconducting magnet warmup shall be tested in the operational facility using available heating capacity of the system.  Temperature control system performance shall be measured during the warmup cycle.

4.5.1.3  Cooldown-Warmup Cycles (ref.  3.2.1.3.2.3)

Test data from warmup and cooldown cycles of the system shall be combined with all subsystem  reliability/maintainability analyses results to verify the capability of the complete system to achieve 100 (TBR) cooldown-warmup cycles.

4.5.1.4  Remote Maintenance (ref. 3.2.5.2.2)

Remote maintainability shall be demonstrated with mock-ups for all remote maintenance category I equipment.

Table 4.5 Quality Conformance Matrix

			Verification Method	

Requirement	
Title	Verification Paragraph	N
/
A	E
XAM	D
E
MO	T
E
S
T	A
N
A
L	
3.2	Characteristics		H					
3.2.1	Performance Characteristics		H					
3.2.1.1	Facility Startup	TBD				X		
3.2.1.2	Reserved		X					
3.2.1.3	Pre-Operational Initialization and Checks		H					
3.2.1.3.1	Pre-Operational Verification		H					
3.2.1.3.2	Magnet Cooldown and Warmup		H					
3.2.1.3.2.1	Magnet Cooldown Timelines	4.5.1.1				X		
3.2.1.3.2.2	Magnet Warmup Timeline	4.5.1.2				X		
3.2.1.3.2.3	Cooldown-Warmup Cycles	4.5.1.3					X	
3.2.1.3.2.4	Coil Quenching	TBD					X	
3.2.1.3.2.5	Cryostat Evacuation Prior to Cooldown	TBD				X		
3.2.1.3.2.6	Use of MFTF-B Refrigerator	TBD			X			
3.2.1.4	Experimental Operations		H					
3.2.1.4.1	Plasma Chamber Conditioning		H					
3.2.1.4.1.1	Base Pressure		H					
3.2.1.4.1.1.1	Base Pressure Development	TBD				X		
3.2.1.4.1.1.2	Impurity Gas Load During Pumpdown	TBD					X	
3.2.1.4.1.2	Bakeout		H					
3.2.1.4.1.2.1	Bakeout Temperatures	TBD				X		
3.2.1.4.1.2.2	Bakeout Timelines	TBD			X			
3.2.1.4.1.3	Glow Discharge Cleaning	TBD					X	
3.2.1.4.1.3.1	GDC Gasses	TBD					X	
3.2.1.4.1.3.2	Use of Hydrogen/Deuterium During GDC	TBD					X	
3.2.1.4.1.3.3	GDC Between Shots	TBD			X 			
3.2.1.4.1.4	Boronization	TBD			X			
3.2.1.4.1.5	Pre-Shot Temperature	TBD				X		
3.2.1.4.2	Plasma Startup		H					
3.2.1.4.2.1	Toroidal Resistance	TBD				X		
3.2.1.4.2.2	Initiation of HC and LC Scenarios	TBD				X		
3.2.1.4.2.3	HC and LC Scenario Startup Sequence	TBD			X			
3.2.1.4.2.4	HC and LC Scenario Coil Currents	TBD				X		
3.2.1.4.2.5	Startup Scenario Variants	TBD				X		
3.2.1.4.3	Plasma Magnetic Field Requirements		H					
3.2.1.4.3.1	Toroidal Field/Plasma Current Directionality	TBD				X		
3.2.1.4.3.2	Toroidal Field Requirements	TBD				X		
3.2.1.4.3.3	Poloidal Field Requirements	TBD				X		
3.2.1.4.3.3.1	Reference Scenarios		H					
3.2.1.4.3.3.1.1	PF Currents for HC and LC Scenarios				X			
3.2.1.4.3.3.1.2	High Current, Double Null (HC) Scenario				X			
3.2.1.4.3.3.1.3	Low Current, Double Null (LC) Scenario				X			
3.2.1.4.3.3.2	Flexibility		H					
3.2.1.4.3.3.2.1	Double Null Divertor Operation							
3.2.1.4.3.3.2.2	Single Null Divertor Operation							
3.2.1.4.3.3.3	Equilibrium Control							
3.2.1.4.3.3.3.1	Radial Plasma Position Control							
3.2.1.4.3.3.3.2	Vertical Plasma Position Control							
3.2.1.4.3.3.3.3	Separatrix Position Control							
3.2.1.4.3.3.3.4	External Kink Mode Control							
3.2.1.4.3.4	Field Errors		H					
3.2.1.4.3.4.1	System Field Error Requirements							
3.2.1.4.3.4.2	FEC Coil Current Requirements							
3.2.1.4.3.4.3	Field Error Requirement and FEC Coil Current Allocations							
3.2.1.4.4	Power Handling							
3.2.1.4.4.1	Scrape-off Layer (SOL) Envelopes							
3.2.1.4.4.2	Maximum Heating Power							
3.2.1.4.4.3	Power Partitioning							
3.2.1.4.5	Disruption Handling							
3.2.1.4.6	Plasma Heating and Current Drive							
3.2.1.4.6.1	Heating and Current Drive Technologies							
3.2.1.4.6.2	Flexibility of Current Density Control							
3.2.1.4.7	Operational Requirements							
3.2.1.4.7.1	Pulse Operation							
3.2.1.4.7.2	Pulse Repetition Rate							
3.2.1.5	Experiment Shutdown							
3.2.1.5.1	Normal Shutdown							
3.2.1.5.2	Abnormal Shutdown							
3.2.1.6	Instrumentation, Control and Data Acquisition							
3.2.1.7	Plasma Diagnostics							
3.2.1.8	Facility Shutdown							
3.2.1.9	Tokamak Fuel							
3.2.1.9.1	Gas Injection							
3.2.1.9.2	Pellet Injection							
3.2.1.10	System Cooling							
3.2.1.11	System Power							
3.2.1.11.1	Allowable Voltage Variation							
3.2.2	System Capability Relationships		H					
3.2.3	External Interface Requirements		H					
3.2.3.1	Commercial Power Interface							
3.2.3.2	Local Water Interface							
3.2.3.3	Data Processing and Remote I&C Interface							
3.2.4	Physical Characteristics		H					
3.2.5	System Quality Factors		H					
3.2.5.1	Reliability						X	
3.2.5.1.1	Mission Reliability						X	
3.2.5.1.2	Shot Reliability						X	
3.2.5.1.2.1	Subsystem Shot Reliability						X	
3.2.5.2	Maintainability		H					
3.2.5.2.1	Scheduled Maintenance						X	
3.2.5.2.2	Remote Maintenance				X			
3.2.5.2.3	Hands-on Maintenance						X	
3.2.5.2.3.1	ICH/FWCD Hands-on Maintenance							
3.2.5.2.4	TPX Assembly and Disassembly							
3.2.5.2.5	Two Man Lift Limits							
3.2.5.2.6	Failure of Fault Detection Equipment							
3.2.5.2.7	Accessibility of Test Points							
3.2.5.2.8	Access to Panels							
3.2.5.2.9	Mean Down Time							
3.2.5.3	Availability							
3.2.5.3.1	Subsystem Availability							
3.2.5.4	Additional Quality Factors							
3.2.5.4.1.1	Annual Operating Limits							
3.2.5.4.1.2	Lifetime Operating Limits							
3.2.6	Environmental Conditions							
3.2.6.1	Natural Environments							
3.2.6.1.1	Temperature (drybulb)							
3.2.6.1.2	Humidity							
3.2.6.1.3	Fungus Growth							
3.2.6.1.4	Sand and Dust							
3.2.6.1.5	Wind							
3.2.6.1.6	Lightning							
3.2.6.1.7	Seismic							
3.2.6.1.8	Solar Heating							
3.2.6.1.9	Atmospheric Pressure							
3.2.6.2	Induced Environments							
3.2.6.2.1	Vibration							
3.2.6.2.2	Shock							
3.2.6.2.3	Neutron Source Rates/Yields							
3.2.6.3	Abnormal Environments							
3.2.6.3.1	Missile Impact							
3.2.7	Transportability							
3.2.8	Flexibility and Expansion							
3.2.8.1	Accommodation of Future Startup Scenarios							
3.2.8.2	Accommodation of  Vacuum Pumping Rate Upgrades							
3.2.8.2.1	Neutral Pressure Vacuum Pumping Rate Upgrade							
3.2.8.2.2	Maximum Pumping Rates Upgrade							
3.2.8.2.3	Minimum Vacuum Pumping Speed Upgrade							
3.2.8.3	Accommodation of Plasma Heating and Current Drive Upgrades							
3.2.8.3.1	Electron Cyclotron Heating/Current Drive Upgrade							
3.2.8.3.1.1	10 MW ECH/ECCD Power							
3.2.8.3.1.2	ECH/ECCD Capabilities							
3.2.8.3.2	Neutral Beam Power Upgrade to 24MW							
3.2.8.3.3	ICH/FWCD Upgrades							
3.2.8.3.3.1	ICH/FWCD Power Upgrade to 18 MW							
3.2.8.3.3.2	ICH/FWCD Operating Frequency Upgrade							
3.2.8.4	Upgrade to Steady State Operation							
3.2.8.4.1	Steady State Operation							
3.2.8.4.2	Steady State Neutral Beam Power							
3.2.8.4.3	Steady State Cooling Capability							
3.2.8.5	Upgrade for Tritium Operation							
3.2.8.6	External Kink Mode Control Upgrade							
3.2.8.7	Diagnostics Upgrades							
3.2.9	Portability							
3.3	Design and Construction							
3.3.1	Materials, Processes, and Parts							
3.3.1.1	Magnetic Permeability							
3.3.1.2	Vacuum Boundary Materials							
3.3.1.3	Structural and Cryogenic Criteria							
3.3.1.4	Corrosion Prevention and Control							
3.3.1.5	Neutral Beam Armor Materials							
3.3.1.6	Divertor Materials							
3.3.1.7	Limiter Materials							
3.3.1.8	Activation							
3.3.2	Electromagnetic Radiation (EMR)							
3.3.2.1	Electrical Referencing Requirements							
3.3.2.2	Electrical bonding							
3.3.2.3	Shielding							
3.3.2.3.1	Equipment cases							
3.3.2.3.2	Shield termination							
3.3.2.3.3	Cable Shield Effectiveness							
3.3.2.4	Electromagnetic Environment							
3.3.2.5	EMI Characteristics							
3.3.2.5.1	Conductors Exiting the Tokamak							
3.3.2.5.2	Tokamak Ports Open to RF Heating Fields							
3.3.2.5.3	Diagnostics Equipment RF Tight Enclosures, Racks, and Cabling							
3.3.3	Nameplates and Product Marking			X				
3.3.3.1	Labels							
3.3.3.2	Identifying Devices							
3.3.4	Workmanship							
3.3.5	Interchangeability							
3.3.6	Environmental, Safety, and Health (ES&H) Requirements							
3.3.6.1	General Safety							
3.3.6.2	Safety Hazards							
3.3.6.2.1	Neutron and Gamma Shielding							
3.3.6.2.2	Radiation Monitoring							
3.3.6.2.3	Controlled Access System							
3.3.6.2.4	Diborane Gas Exposure							
3.3.6.3	Personnel Safety							
3.3.6.4	Flammability							
3.3.6.5	Fire Suppression							
3.3.6.6	Hazardous Materials							
3.3.6.6.1	Activated Air Emissions							
3.3.6.6.2	Hazardous Liquid Containment							
3.3.6.7	Electrical Safety							
3.3.6.8	Radiological Design Objectives							
3.3.7	Human Engineering							
3.3.7.1	Anthropometry							
3.3.7.2	Human Environments							
3.3.7.2.1	Temperature and Humidity							
3.3.7.2.2	Ventilation							
3.3.7.2.3	Lighting							
3.3.7.2.4	Emergency Lighting							
3.3.7.2.5	Noise							
3.3.7.2.6	Vibration							
3.3.7.3	Component Arrangement							
3.3.7.4	Protective Equipment							
3.3.7.5	Display Devices							
3.3.7.6	System Controls							
3.3.7.6.1.1	Operator Controls							
3.3.7.6.2	Component Controls							
3.3.7.7	Warning and Annunciator Systems							
3.3.7.8	Communications Systems							
3.3.8	Nuclear Control							
3.3.9	System Security							
3.3.10 	Government Furnished Property Usage							
3.3.11	Computer Resource Reserve Capacity							
3.4	Documentation							
3.5	Logistics							
3.5.1	Maintenance							
3.5.1.1	Test Cell Maintenance							
3.5.1.1.1	Hands-on Maintenance							
3.5.1.1.2	Remote Maintenance							
3.5.2	Supply							
3.5.3	Facility Maintenance							
3.6	Personnel and Training							
3.6.1	Personnel							
3.6.2	Training							
3.7	Characteristics of Subordinate Elements							
3.7.1	Plasma Facing Components (PFC)							
3.7.1.1	Resistive Breaks							
3.7.1.2	Component Power Handling Requirements							
3.7.1.2.1	Divertor Power Handling							
3.7.1.2.2	Inner Toroidal Limiter Power Handling							
3.7.1.2.3	Outer Toroidal Limiter Power Handling							
3.7.1.2.4	Neutral Beam Armor Power Handling							
3.7.1.2.5	Poloidal Limiters Power Handling							
3.7.1.2.6	Other Line-of-Sight Components Power Handling							
3.7.1.3	Divertor Configuration							
3.7.1.3.1	Peak Heat Load Reduction							
3.7.1.3.2	High Heat Flux Region Geometry							
3.7.1.3.3	Maximum Auxiliary Baffle Leak Rate							
3.7.1.3.4	Divertor Assembly Reconfiguration							
3.7.1.4	Limiter Configuration							
3.7.2	Vacuum Vessel (VV) System							
3.7.2.1	Base Pressure							
3.7.2.2	Leak Rate							
3.7.2.3	Alignment and Operational Stability							
3.7.2.4	Toroidal Resistance							
3.7.3	Toroidal Field (TF) System							
3.7.4	Poloidal Field (PF) System							
3.7.5	Cryostat							
3.7.6	Tokamak Support Structure							
3.7.7	Tokamak Assembly							
3.7.8	Tokamak Shielding							
3.7.9	FEC and FPPC Coil Systems							
3.7.9.1	FEC Coil System							
3.7.9.2	FPPC Coil System							
3.7.10	Neutral Beam System							
3.7.10.1	8MW Neutral Beam Power							
3.7.10.2	Beamline Orientation							
3.7.11	Electron Cyclotron Heating and Current Drive							
3.7.12	Ion Cyclotron Heating and Fast Wave Current Drive							
3.7.12.1	6MW ICH/FWCD Power							
3.7.12.2	ICH/FWCD Power at a Single Frequency							
3.7.12.3	ICH/FWCD Power at Three  Frequencies							
3.7.12.4	Use of Faraday Shield							
3.7.13	Lower Hybrid Heating and Current Drive (LHH/LHCD)							
3.7.13.1	3MW LHH/LHCD Power							
3.7.13.2	Dynamic Variance of Wave Number Spectrum							
3.7.13.3	Surface Configuration of LH Launcher							
3.7.13.4	Movement of LH Launcher							
3.7.14	Fuel Storage and Delivery Systems							
3.7.15	Pellet Injection System							
3.7.16	Radiation Monitoring and Tritium Cleanup Systems							
3.7.17	Vacuum Pumping System							
3.7.17.1	Vacuum Pumping Speed and Throughput							
3.7.17.1.1	Neutral Pressure Vacuum Pumping Rates							
3.7.17.1.2	Maximum Vacuum Pumping Rates							
3.7.17.1.3	Minimum Vacuum Pumping Speeds							
3.7.17.1.4	Vacuum Pumping Speed Control							
3.7.18	Power Systems							
3.7.19	Maintenance Systems							
3.7.20	Central I&C System							
3.7.21	Plasma Diagnostics							
3.7.21.1	Plasma Control Diagnostics							
3.7.21.2	Confinement Diagnostics							
3.7.21.3	Divertor/Edge Plasma Diagnostics							
3.7.21.4	Fusion Yield Diagnostics							
3.7.21.5	Baseline diagnostics							
3.7.22	Building, Modifications, and Site Improvements							
3.7.23	Cryogenic Systems							
3.7.24	Water Systems							
3.7.24.1	50°C Cooling Water System							
3.7.24.2	Borated Water System							
3.7.24.3	Bakeout System							
3.7.24.4	Chilled Water System							
3.7.24.5	Demineralized Cooling Water System							
3.7.24.6	Heat Rejection System							
3.7.24.7	Makeup Water System							
3.7.24.8	Gas Blanket and Vent System							
3.7.25	Test Cell Penetrations							
3.8	Precedence							
3.9	Qualification							
3.10 	Standard Sample							
3.11	Preproduction Sample							
	H=Heading 
	T=TBD

5.  PREPARATION FOR DELIVERY
This paragraph is not applicable to this specification.

6.  NOTES
6.1  Requirement References

The following documents represent requirement sources for the requirements contained within this specification:

[1]	TPX Project Work Breakdown Structure (WBS) Dictionary, TPX Project Management Plan Appendix A-2, TPX-PLAN-PMP Rev. 2
	
[2]	LCTF Superconducting TF Coil Technical Specification, TS14700-01 Rev. E
	
[3]	TF (WBS 13) System Design Description
	
[4]	PF (WBS 14) System Design Description
	
[5]	"PHPK, Inc., MFTF-B Refrigerator Analysis Report", Felker to Distribution, 72-950328-LLNL-BFelker-01
	
[6]	VV (WBS 12) System Design Description
	
[7]	TPX Structural and Cryogenic Design Criteria, TPX-STND-001 Rev. 1
	
[8]	"TPX PF Flexibility Assessment", Bulmer to Neilson, 93-950601-LLNL-Bulmer-01
	
[9]	"TPX High Current Design Basis Scenario", Bulmer to Neilson, 93-950120-LLNL-RBulmer-01
	
[10]	"Low Current Scenario", Bulmer to Neilson, 93-950605-LLNL-RBulmer-01
	
[11]	"The Impact of the Cryostat on Startup for TPX, Rev. 1", Wang to Distribution, 14-940803-MIT/PWang-01
	
[12]	General Requirements Document (GRD), TPX-RQMT-GRD Rev. 1
	
[13]	Project Definition Statement (PDS), TPX-RQMT-PDS Rev. 2
	
[14]	TPX Seismic Design Criteria, TPX-STND-002 Rev. 0
	
[15]	TPX Grounding for Equipment and Personnel Safety, TPX-STND-004 Rev. 0
	
[16]	"Improved Radial Positioning With All Coil Pairs", Bulmer to Pillsbury, 93-950501-LLNL-RBulmer-01
	
[17]	"Strike Point Positioning With All Coil Pairs", Bulmer to Pillsbury, 93-950330-LLNL-RBulmer-01
	
[18]	"TPX Equilibria With TF Coil Lead Asymmetry", Bulmer to Neilson, 93-950117-LLNL-RBulmer-01

6.2  Field Error Calculation

This section contains backup information on how to calculate the requirements for the FEC coil capability to limit field errors (n=1 and n=2) from Section 3.2.1.4.3.4.

dBrm,1 is the complex amplitude of the helical Fourier component, with poloidal harmonic number m and toroidal harmonic number n  equal to 1, of the radial component of the magnetic field. The definition of dBrm,n is:

when Fourier analyzed on a toroidal surface with a dee-shaped cross section defined parametrically by:

where R0=2.25 m, =0.5 m, =1.8, and d=0.5.

The poloidal angle q to be used in the Fourier analysis is defined as a function of the poloidal parameter Q by:

The unit vector  is defined as:

where  are unit vectors in the R and Z directions, respectively, and

6.3  Definitions

Availability

Availability is the ratio of the number of shots in an operational run period in which the device is operational at its rated performance level for the planned duration of the shot to the number of shots which could be achieved during that run period in the absence of component failures and software errors

Beta (Normalized)

The normalized beta (bN) is equal to

where Ip is the plasma current (in MA), a is the plasma minor radius (in m), B is the vacuum toroidal field at the major radius (in T), and <b> is the volume-averaged b.

Mean Down Time

Mean down time (MDT) is defined as the total elapsed time from loss of operational capability to return to operational capability.  MDT includes any delays for shutdown of the system or subsystems, delays for spares or maintenance equipment, fault isolation, corrective maintenance, checkout of repairs, removal of personnel and/or maintenance equipment, and system start-up.

Mean Time To Repair

The measure of maintainability is MTTR.  It is the sum of corrective maintenance times divided by the total number of failures.  MTTR starts when the faulty item is positioned for maintenance and a qualified maintenance crew is available.  It includes gaining access to the equipment, positioning maintenance support equipment, fault isolation, on-equipment repair, check-out, and installation of access covers or panels.

Mission Reliability

Mission reliability is the probability of the TPX program not being terminated due to equipment or software failures (TBR).

Operating Conditions

Table 6.3 defines general design guidelines for events relative to their probability of occurrence.

Plasma Major Radius

The plasma major radius (Ro) is the radius from the major axis to the center of the plasma on the midplane.

Plasma Minor Radius

The plasma minor radius is the half width of the plasma on the midplane.

Rated Performance Level

The TPX rated performance level is TBD.

Recovery

Recovery is all design related failure modes prevention, mitigation, or correction that will reduce the risk of TPX program termination.

Remote Maintenance Categories 

Equipment for which maintenance (scheduled or unscheduled) is a normal or anticipated event is designated as Category I equipment.  All other equipment requiring remote maintenance is designated as Category II equipment.
Table 6.3  General Design Guidelines for Potential Events

Operating Condition	Description	P, Probability of Occurrence in A Year	General Design Guidelines	
Normal Events	Events that are planned to occur regularly in the course of facility operation.	P=1	Provide safe and reliable operation.	
Anticipated Events	Events of moderate frequency which may occur once or more in the lifetime of the facility.	1>P≥10-2	The facility should be capable of returning to operation without extensive corrective action or repair.	
Unlikely Events	Events which are not anticipated but which may occur during the lifetime of the facility.	10-2≥10-4	The facility should be capable of returning to operation following potentially extensive corrective actions or repairs, as necessary.	
Extremely Unlikely Events	Events which are limiting faults and are not expected to occur during the lifetime of the facility but are postulated because of their safety consequences.	10-4>P≥10-6	Facility damage may preclude returning to operation.	
Incredible Events	Events of extremely low probability of occurrence or of non-mechanistic origin.	P<10-6	Not considered in the design.	

Shot

A shot is when the TPX is performing experimental operations during the period of constant plasma current.  A shot begins when a breakdown loop voltage pulse is applied to initiate a plasma and ends upon plasma shutdown (TBR).

Shot Reliability

The probability of the necessary subset of data for achieving the goal of a given shot being successfully acquired and archived; and not experiencing a failure precluding the initiation of the next shot.

Steady State

The state or condition of the system that does not change over time for a 100,000 second shot of constant plasma current.(TBR)

6.4  Acronyms

AC	Alternating Current	
CAM	Compliance and Allocation Matrix	
CAS	Controlled Access System	
CI	Configuration Item	
CICC	Cable-in-Conduit-Conductor	
CS	Central Solenoid	
D	Deuterium	
DBA	Design Basis Accident	
DBE	Design Basis Earthquake	
DC	Direct Current	
DD	Deuterium-Deuterium Fusion Reactions	
DOE	Department of Energy	
DT	Deuterium-Tritium Fusion Reactions	
ECCD	Electron Cyclotron Current Drive	
ECH	Electron Cyclotron Heating System	
ECP	Engineering Change Proposal	
ECS	Environmental Control System	
EH	DOE Office of Environmental Health 	
EIS	Environmental Impact Statement	
EME	Electromagnetic Environment	
EMI	Electromagnetic Interference	
EOB	End of Beta	
EPA	Environmental Protection Agency	
ER	DOE Office of Energy Research	
ES&H	Environment, Safety, and Health	
ES&H/EB	PPPL ES&H Executive Board	
ESHD	Environmental Safety and Health Directive	
FEC	Field Error Correction	
FPPC	Fast Plasma Position Control Coils	
GA	General Atomics	
GDC	Glow Discharge Cleaning	
GFE	Government Furnished Equipment	
GFI	Government Furnished Information	
GFS	Government Furnished Software	
GRD	General Requirements Document	
H	Hydrogen	
HC	High Current, Double Null Divertor Scenario	
He	Helium	
HVAC	Heating Ventilation and Air Conditioning	
I&C	Instrumentation and Control	
Ibs/Ip	Ratio of Bootstrap Current to Plasma Current	
ICH	Ion Cyclotron Heating System	
LC	Low Current, Double Null Divertor Scenario	
LHCD	Lower Hybrid Heating/Current Drive	
LHe	Liquid Helium	
LHH	Lower Hybrid Heating	
LLNL	Lawrence Livermore National Laboratory	
MDT	Mean Downtime	
MFTF	Mirror Fusion Test Facility	
MTBF	Mean Time Between Failure	
MTTR	Mean Time To Repair	
NB	Neutral Beam	
NBI	Neutral Beam Injection System	
NEPA	National Environmental Protection Act (1969)	
NESHAPS	National Emission Standards for Hazardous Air Pollutants	
NFPA	National Fire Protection Association	
NJPDES	New Jersey Pollutant Discharge Elimination System	
OSHA	Occupational Safety and Health Administration	
PC	Performance Class	
PDD	Physics Design Description	
PDS	Project Definition Statement	
PEL	Permissible Exposure Limit	
p.f.	Power Factor	
PF	Poloidal Field	
PFC	Plasma Facing Components	
PPPL	Princeton Plasma Physics Laboratory	
PSE&G	Public Service Electric and Gas Company	
RAM	Reliability, Availability, and Maintainability	
RF	Radio Frequency	
RH	Relative Humidity	
SDD	Systems Design Description	
SOB	Start of Beta	
SOF	Start of Flattop	
SOL	Scrape-Off Layer	
SRD	Systems Requirements Document	
TBD	To Be Determined	
TBR	To Be Revised	
TEP	Test and Evaluation Plan	
TF	Toroidal Field	
TFTR	Tokamak Fusion Test Reactor	
TPWG	Test Planning Working Group	
TPX	Tokamak Physics Experiment	
TSR	Technical Safety Requirements	
VV	Vacuum Vessel	
WBS	Work Breakdown Structure	

TPX 

System Specification

TPX-RQMT-ASPEC Rev. 0, Draft C

SEPTEMBER 22, 1995
APPENDIX I - PF COIL CURRENT REQUIREMENTS

95-950922-TRW-DJohnson-01

10.1  PF Coil Current Requirements

TABLE 10.1-1 PF COIL GEOMETRY DEFINITION FOR EQUILIBRIA

References	PF coil geometry @ 5K defined in TPX E-9414002 P1 Sheet 2
	PF equilibria geometry (per [8] 93-950601-LLNL-RBulmer-01) same as above
	IC coil geometry defined in TPX E-9419202 P0 Sheet 1
	TF compensation currents per [18] 93-950117-LLNL-RBulmer-01 for 33.5kA (-4T)		

	R(m)	Z(m)	DR(m)	DZ(m)	Itf, comp (MAT)	Turns	
PF1/U	0.810	0.251	0.143	0.477	0.000	120	
PF2/U	0.810	0.706	0.143	0.382	0.000	96	
PF3/U	0.810	1.042	0.143	0.239	0.003	60	
PF4/U	0.810	1.306	0.143	0.239	0.002	60	
PF5/U	1.213	2.350	0.191	0.382	-0.019	128	
PF6/U	3.758	2.144	0.143	0.477	-0.027	120	
PF7/U	4.297	1.114	0.143	0.335	0.000	84	
FPPC/U	2.940	0.685	0.069	0.109	0.000	4	
PF1/L	0.810	-0.251	0.143	0.477	0.000	120	
PF2/L	0.810	-0.706	0.143	0.382	0.000	96	
PF3/L	0.810	-1.042	0.143	0.239	-0.001	60	
PF4/L	0.810	-1.306	0.143	0.239	0.000	60	
PF5/L	1.213	-2.350	0.191	0.382	0.001	128	
PF6/L	3.758	-2.144	0.143	0.477	-0.002	120	
PF7/L	4.297	-1.114	0.143	0.335	0.000	84	
FPPC/L	2.940	-0.685	0.069	0.109	0.000	4	

TABLE 10.1-2 q=3 DN FLEXIBILITY POINTS [B=-4T]

	D(R+a)=0, DRsep=0, DZosp=0
li, bN	0.4, 5.0	0.5, 2.2	0.7,0.0	1.2, 0.0	1.2, 5.0	
PF1/U	-1.443	-2.357	-3.032	-3.017	-2.432	
PF2/U	-2.230	-1.964	-0.567	0.481	-0.500	
PF3/U	-0.957	-0.690	0.192	0.732	0.099	
PF4/U	-0.736	-0.467	0.394	0.866	0.241	
PF5/U	3.231	2.903	3.375	3.074	2.514	
PF6/U	-2.182	-2.231	-1.734	-0.539	-0.681	
PF7/U	-0.389	-0.110	-0.171	-0.929	-1.309	
FPPC/U	0.000	0.000	0.000	0.000	0.000	
PF1/L	-1.443	-2.357	-3.032	-3.017	-2.432	
PF2/L	-2.230	-1.964	-0.567	0.481	-0.500	
PF3/L	-0.961	-0.694	0.188	0.728	0.095	
PF4/L	-0.738	-0.469	0.392	0.864	0.239	
PF5/L	3.251	2.923	3.395	3.094	2.534	
PF6/L	-2.157	-2.206	-1.709	-0.514	-0.656	
PF7/L	-0.389	-0.110	-0.171	-0.929	-1.309	
FPPC/L	0.000	0.000	0.000	0.000	0.000	
TF	0.034	0.034	0.034	0.034	0.034	
PLASMA	2.000	2.000	2.000	2.000	1.937	

TABLE 10.1-3 q=3 DN FLEXIBILITY POINTS [B=+4T]

	D(R+a)=0, DRsep=0, DZosp=0
li, bN	0.4, 5.0	0.5, 2.2	0.7,0.0	1.2, 0.0	1.2, 5.0	
PF1/U	-1.443	-2.357	-3.032	-3.017	-2.432	
PF2/U	-2.230	-1.964	-0.567	0.481	-0.500	
PF3/U	-0.963	-0.696	0.186	0.726	0.093	
PF4/U	-0.740	-0.471	0.390	0.862	0.237	
PF5/U	3.269	2.941	3.413	3.112	2.552	
PF6/U	-2.128	-2.177	-1.680	-0.485	-0.627	
PF7/U	-0.389	-0.110	-0.171	-0.929	-1.309	
FPPC/U	0.000	0.000	0.000	0.000	0.000	
PF1/L	-1.443	-2.357	-3.032	-3.017	-2.432	
PF2/L	-2.230	-1.964	-0.567	0.481	-0.500	
PF3/L	-0.959	-0.692	0.190	0.730	0.097	
PF4/L	-0.738	-0.469	0.392	0.864	0.239	
PF5/L	3.249	2.921	3.393	3.092	2.532	
PF6/L	-2.153	-2.202	-1.705	-0.510	-0.652	
PF7/L	-0.389	-0.110	-0.171	-0.929	-1.309	
FPPC/L	0.000	0.000	0.000	0.000	0.000	
TF	-0.034	-0.034	-0.034	-0.034	-0.034	
PLASMA	2.000	2.000	2.000	2.000	1.937	

TABLE 10.1-4 q=3 DN RADIAL POSITION CONTROL [B=-4T]

	D(R+a)=-2cm
li, bN	0.4, 5.0	0.5, 2.2	0.7,0.0	1.2, 0.0	1.2, 5.0	
PF1/U	-1.292	-2.318	-2.997	-2.776	-2.103	
PF2/U	-2.402	-2.058	-0.703	0.384	-0.377	
PF3/U	-1.076	-0.773	0.111	0.650	0.136	
PF4/U	-0.856	-0.551	0.317	0.786	0.282	
PF5/U	3.179	2.950	3.322	3.191	3.009	
PF6/U	-2.170	-2.195	-1.840	-0.551	-0.720	
PF7/U	-0.400	-0.134	-0.096	-0.930	-1.284	
FPPC/U	0.000	0.000	0.000	0.000	0.000	
PF1/L	-1.292	-2.318	-2.997	-2.776	-2.103	
PF2/L	-2.402	-2.058	-0.703	0.384	-0.377	
PF3/L	-1.080	-0.777	0.107	0.646	0.132	
PF4/L	-0.858	-0.553	0.315	0.784	0.280	
PF5/L	3.199	2.970	3.342	3.211	3.029	
PF6/L	-2.145	-2.170	-1.815	-0.526	-0.695	
PF7/L	-0.400	-0.134	-0.096	-0.930	-1.284	
FPPC/L	0.000	0.000	0.000	0.000	0.000	
TF	0.034	0.034	0.034	0.034	0.034	
PLASMA	2.000	2.000	2.000	2.000	1.937	

	D(R+a)=+2cm
li, bN	0.4, 5.0	0.5, 2.2	0.7,0.0	1.2, 0.0	1.2, 5.0	
PF1/U	-1.679	-2.590	-3.152	-3.279	-2.553	
PF2/U	-2.247	-1.890	-0.566	0.570	-0.180	
PF3/U	-0.943	-0.619	0.202	0.813	0.285	
PF4/U	-0.726	-0.397	0.400	0.944	0.415	
PF5/U	2.940	2.777	3.195	2.914	2.619	
PF6/U	-2.157	-2.240	-1.620	-0.511	-0.606	
PF7/U	-0.381	-0.091	-0.260	-0.938	-1.315	
FPPC/U	0.000	0.000	0.000	0.000	0.000	
PF1/L	-1.679	-2.590	-3.152	-3.279	-2.553	
PF2/L	-2.247	-1.890	-0.566	0.570	-0.180	
PF3/L	-0.947	-0.623	0.198	0.809	0.281	
PF4/L	-0.728	-0.399	0.398	0.942	0.413	
PF5/L	2.960	2.797	3.215	2.934	2.639	
PF6/L	-2.132	-2.215	-1.595	-0.486	-0.581	
PF7/L	-0.381	-0.091	-0.260	-0.938	-1.315	
FPPC/L	0.000	0.000	0.000	0.000	0.000	
TF	0.034	0.034	0.034	0.034	0.034	
PLASMA	2.000	2.000	2.000	2.000	1.937	

TABLE 10.1-5 q=3 DN RADIAL POSITION CONTROL [B=+4T]

	D(R+a)=-2cm
li, bN	0.4, 5.0	0.5, 2.2	0.7,0.0	1.2, 0.0	1.2, 5.0	
PF1/U	-1.292	-2.318	-2.997	-2.776	-2.103	
PF2/U	-2.402	-2.058	-0.703	0.384	-0.377	
PF3/U	-1.082	-0.779	0.105	0.644	0.130	
PF4/U	-0.860	-0.555	0.313	0.782	0.278	
PF5/U	3.217	2.988	3.360	3.229	3.047	
PF6/U	-2.116	-2.141	-1.786	-0.497	-0.666	
PF7/U	-0.400	-0.134	-0.096	-0.930	-1.284	
FPPC/U	0.000	0.000	0.000	0.000	0.000	
PF1/L	-1.292	-2.318	-2.997	-2.776	-2.103	
PF2/L	-2.402	-2.058	-0.703	0.384	-0.377	
PF3/L	-1.078	-0.775	0.109	0.648	0.134	
PF4/L	-0.858	-0.553	0.315	0.784	0.280	
PF5/L	3.197	2.968	3.340	3.209	3.027	
PF6/L	-2.141	-2.166	-1.811	-0.522	-0.691	
PF7/L	-0.400	-0.134	-0.096	-0.930	-1.284	
FPPC/L	0.000	0.000	0.000	0.000	0.000	
TF	-0.034	-0.034	-0.034	-0.034	-0.034	
PLASMA	2.000	2.000	2.000	2.000	1.937	

	D(R+a)=+2cm
li, bN	0.4, 5.0	0.5, 2.2	0.7,0.0	1.2, 0.0	1.2, 5.0	
PF1/U	-1.679	-2.590	-3.152	-3.279	-2.553	
PF2/U	-2.247	-1.890	-0.566	0.570	-0.180	
PF3/U	-0.949	-0.625	0.196	0.807	0.279	
PF4/U	-0.730	-0.401	0.396	0.940	0.411	
PF5/U	2.978	2.815	3.233	2.952	2.657	
PF6/U	-2.103	-2.186	-1.566	-0.457	-0.552	
PF7/U	-0.381	-0.091	-0.260	-0.938	-1.315	
FPPC/U	0.000	0.000	0.000	0.000	0.000	
PF1/L	-1.679	-2.590	-3.152	-3.279	-2.553	
PF2/L	-2.247	-1.890	-0.566	0.570	-0.180	
PF3/L	-0.945	-0.621	0.200	0.811	0.283	
PF4/L	-0.728	-0.399	0.398	0.942	0.413	
PF5/L	2.958	2.795	3.213	2.932	2.637	
PF6/L	-2.128	-2.211	-1.591	-0.482	-0.577	
PF7/L	-0.381	-0.091	-0.260	-0.938	-1.315	
FPPC/L	0.000	0.000	0.000	0.000	0.000	
TF	-0.034	-0.034	-0.034	-0.034	-0.034	
PLASMA	2.000	2.000	2.000	2.000	1.937	

TABLE 10.1-6 q=3 DN STRIKE PT POSITION CONTROL [B=-4T]

	DZosp=-5cm
li, bN	0.4, 5.0	0.5, 2.2	0.7,0.0	1.2, 0.0	1.2, 5.0	
PF1/U	-1.337	-2.230	-2.969	-2.943	-2.233	
PF2/U	-2.495	-2.121	-0.746	0.390	-0.388	
PF3/U	-1.103	-0.779	0.089	0.675	0.151	
PF4/U	-0.858	-0.537	0.302	0.815	0.303	
PF5/U	3.344	3.108	3.455	3.216	3.012	
PF6/U	-2.247	-2.279	-1.773	-0.569	-0.713	
PF7/U	-0.350	-0.086	-0.162	-0.919	-1.277	
FPPC/U	0.000	0.000	0.000	0.000	0.000	
PF1/L	-1.337	-2.230	-2.969	-2.943	-2.233	
PF2/L	-2.495	-2.121	-0.746	0.390	-0.388	
PF3/L	-1.107	-0.783	0.085	0.671	0.147	
PF4/L	-0.860	-0.539	0.300	0.813	0.301	
PF5/L	3.364	3.128	3.475	3.236	3.032	
PF6/L	-2.222	-2.254	-1.748	-0.544	-0.688	
PF7/L	-0.350	-0.086	-0.162	-0.919	-1.277	
FPPC/L	0.000	0.000	0.000	0.000	0.000	
TF	0.034	0.034	0.034	0.034	0.034	
PLASMA	2.000	2.000	2.000	2.000	1.937	

	DZosp=+5cm
li, bN	0.4, 5.0	0.5, 2.2	0.7,0.0	1.2, 0.0	1.2, 5.0	
PF1/U	-1.608	-2.468	-3.162	-3.088	-2.399	
PF2/U	-2.186	-1.855	-0.542	0.543	-0.191	
PF3/U	-0.932	-0.629	0.214	0.774	0.258	
PF4/U	-0.733	-0.422	0.408	0.904	0.384	
PF5/U	2.847	2.668	3.094	2.929	2.651	
PF6/U	-2.131	-2.183	-1.702	-0.515	-0.628	
PF7/U	-0.400	-0.122	-0.186	-0.937	-1.312	
FPPC/U	0.000	0.000	0.000	0.000	0.000	
PF1/L	-1.608	-2.468	-3.162	-3.088	-2.399	
PF2/L	-2.186	-1.855	-0.542	0.543	-0.191	
PF3/L	-0.936	-0.633	0.210	0.770	0.254	
PF4/L	-0.735	-0.424	0.406	0.902	0.382	
PF5/L	2.867	2.688	3.114	2.949	2.671	
PF6/L	-2.106	-2.158	-1.677	-0.490	-0.603	
PF7/L	-0.400	-0.122	-0.186	-0.937	-1.312	
FPPC/L	0.000	0.000	0.000	0.000	0.000	
TF	0.034	0.034	0.034	0.034	0.034	
PLASMA	2.000	2.000	2.000	2.000	1.937	

TABLE 10.1-7 q=3 DN STRIKE PT POSITION CONTROL [B=+4T]

	DZosp=-5cm
li, bN	0.4, 5.0	0.5, 2.2	0.7,0.0	1.2, 0.0	1.2, 5.0	
PF1/U	-1.337	-2.230	-2.969	-2.943	-2.233	
PF2/U	-2.495	-2.121	-0.746	0.390	-0.388	
PF3/U	-1.109	-0.785	0.083	0.669	0.145	
PF4/U	-0.862	-0.541	0.298	0.811	0.299	
PF5/U	3.382	3.146	3.493	3.254	3.050	
PF6/U	-2.193	-2.225	-1.719	-0.515	-0.659	
PF7/U	-0.350	-0.086	-0.162	-0.919	-1.277	
FPPC/U	0.000	0.000	0.000	0.000	0.000	
PF1/L	-1.337	-2.230	-2.969	-2.943	-2.233	
PF2/L	-2.495	-2.121	-0.746	0.390	-0.388	
PF3/L	-1.105	-0.781	0.087	0.673	0.149	
PF4/L	-0.860	-0.539	0.300	0.813	0.301	
PF5/L	3.362	3.126	3.473	3.234	3.030	
PF6/L	-2.218	-2.250	-1.744	-0.540	-0.684	
PF7/L	-0.350	-0.086	-0.162	-0.919	-1.277	
FPPC/L	0.000	0.000	0.000	0.000	0.000	
TF	-0.034	-0.034	-0.034	-0.034	-0.034	
PLASMA	2.000	2.000	2.000	2.000	1.937	

	DZosp=+5cm
li, bN	0.4, 5.0	0.5, 2.2	0.7,0.0	1.2, 0.0	1.2, 5.0	
PF1/U	-1.608	-2.468	-3.162	-3.088	-2.399	
PF2/U	-2.186	-1.855	-0.542	0.543	-0.191	
PF3/U	-0.938	-0.635	0.208	0.768	0.252	
PF4/U	-0.737	-0.426	0.404	0.900	0.380	
PF5/U	2.885	2.706	3.132	2.967	2.689	
PF6/U	-2.077	-2.129	-1.648	-0.461	-0.574	
PF7/U	-0.400	-0.122	-0.186	-0.937	-1.312	
FPPC/U	0.000	0.000	0.000	0.000	0.000	
PF1/L	-1.608	-2.468	-3.162	-3.088	-2.399	
PF2/L	-2.186	-1.855	-0.542	0.543	-0.191	
PF3/L	-0.934	-0.631	0.212	0.772	0.256	
PF4/L	-0.735	-0.424	0.406	0.902	0.382	
PF5/L	2.865	2.686	3.112	2.947	2.669	
PF6/L	-2.102	-2.154	-1.673	-0.486	-0.599	
PF7/L	-0.400	-0.122	-0.186	-0.937	-1.312	
FPPC/L	0.000	0.000	0.000	0.000	0.000	
TF	-0.034	-0.034	-0.034	-0.034	-0.034	
PLASMA	2.000	2.000	2.000	2.000	1.937	

TABLE 10.1-8 q=3 DN VERTICAL POSITION CONTROL [B=-4T]

[TBD]

TABLE 10.1-9 q=3 DN VERTICAL POSITION CONTROL [B=+4T]

[TBD]

TABLE 10.1-10 q=5 DN FLEXIBILITY POINTS [B=-4T]

li, bN	0.4,7.0	0.4,5.0	0.7, 0.0	1.5, 0.0	1.5, 7.0	
PF1/U	-0.941	-1.083	-2.045	-1.752	-0.494	
PF2/U	-2.027	-1.918	-0.459	0.672	0.361	
PF3/U	-0.916	-0.845	0.083	0.635	0.305	
PF4/U	-0.724	-0.662	0.217	0.691	0.365	
PF5/U	2.648	2.551	2.093	1.746	2.555	
PF6/U	-1.616	-1.753	-1.160	0.077	0.037	
PF7/U	-0.760	-0.424	-0.114	-0.780	-1.296	
FPPC/U	0.000	0.000	0.000	0.000	0.000	
PF1/L	-0.941	-1.083	-2.045	-1.752	-0.494	
PF2/L	-2.027	-1.918	-0.459	0.672	0.361	
PF3/L	-0.920	-0.849	0.079	0.631	0.301	
PF4/L	-0.726	-0.664	0.215	0.689	0.363	
PF5/L	2.668	2.571	2.113	1.766	2.575	
PF6/L	-1.591	-1.728	-1.135	0.102	0.062	
PF7/L	-0.760	-0.424	-0.114	-0.780	-1.296	
FPPC/L	0.000	0.000	0.000	0.000	0.000	
TF	0.034	0.034	0.034	0.034	0.034	
PLASMA	1.719	1.608	1.312	1.153	1.172	

TABLE 10.1-11 q=5 DN FLEXIBILITY POINTS [B=+4T]

li, bN	0.4,7.0	0.4,5.0	0.7, 0.0	1.5, 0.0	1.5, 7.0	
PF1/U	-0.941	-1.083	-2.045	-1.752	-0.494	
PF2/U	-2.027	-1.918	-0.459	0.672	0.361	
PF3/U	-0.922	-0.851	0.077	0.629	0.299	
PF4/U	-0.728	-0.666	0.213	0.687	0.361	
PF5/U	2.686	2.589	2.131	1.784	2.593	
PF6/U	-1.562	-1.699	-1.106	0.131	0.091	
PF7/U	-0.760	-0.424	-0.114	-0.780	-1.296	
FPPC/U	0.000	0.000	0.000	0.000	0.000	
PF1/L	-0.941	-1.083	-2.045	-1.752	-0.494	
PF2/L	-2.027	-1.918	-0.459	0.672	0.361	
PF3/L	-0.918	-0.847	0.081	0.633	0.303	
PF4/L	-0.726	-0.664	0.215	0.689	0.363	
PF5/L	2.666	2.569	2.111	1.764	2.573	
PF6/L	-1.587	-1.724	-1.131	0.106	0.066	
PF7/L	-0.760	-0.424	-0.114	-0.780	-1.296	
FPPC/L	0.000	0.000	0.000	0.000	0.000	
TF	-0.034	-0.034	-0.034	-0.034	-0.034	
PLASMA	1.719	1.608	1.312	1.153	1.172	

TABLE 10.1-12 q=3 SN FLEXIBILITY POINTS [B=-4T]

	Lower SN
li, bN	0.4, 5.0	0.5, 2.2	0.7,0.0	1.2, 0.0	1.2, 5.0	
PF1/U	-1.518	-2.534	-3.000	-2.526	-1.883	
PF2/U	-2.271	-1.805	-0.717	-0.239	-0.358	
PF3/U	-0.591	-0.249	0.328	0.144	0.128	
PF4/U	-0.151	0.042	0.446	0.292	0.203	
PF5/U	1.661	1.366	1.833	2.138	1.142	
PF6/U	-1.768	-1.840	-1.461	-0.111	-0.106	
PF7/U	-0.457	-0.167	-0.189	-0.941	-1.292	
FPPC/U	0.000	0.000	0.000	0.000	0.000	
PF1/L	-1.518	-2.534	-3.000	-2.526	-1.883	
PF2/L	-2.271	-1.805	-0.717	-0.239	-0.358	
PF3/L	-0.953	-0.715	-0.167	0.377	0.052	
PF4/L	-0.791	-0.495	0.081	0.506	0.191	
PF5/L	3.368	3.132	3.380	2.614	2.584	
PF6/L	-2.176	-2.268	-1.838	-0.595	-0.575	
PF7/L	-0.457	-0.167	-0.189	-0.941	-1.292	
FPPC/L	0.000	0.000	0.000	0.000	0.000	
TF	0.034	0.034	0.034	0.034	0.034	
PLASMA	2.000	2.000	2.000	1.801	1.714	

	Upper SN
li, bN	0.4, 5.0	0.5, 2.2	0.7,0.0	1.2, 0.0	1.2, 5.0	
PF1/U	-1.518	-2.534	-3.000	-2.526	-1.883	
PF2/U	-2.271	-1.805	-0.717	-0.239	-0.358	
PF3/U	-0.952	-0.714	-0.166	0.378	0.053	
PF4/U	-0.791	-0.495	0.081	0.506	0.191	
PF5/U	3.367	3.131	3.379	2.613	2.583	
PF6/U	-2.174	-2.266	-1.836	-0.593	-0.573	
PF7/U	-0.457	-0.167	-0.189	-0.941	-1.292	
FPPC/U	0.000	0.000	0.000	0.000	0.000	
PF1/L	-1.518	-2.534	-3.000	-2.526	-1.883	
PF2/L	-2.271	-1.805	-0.717	-0.239	-0.358	
PF3/L	-0.594	-0.252	0.325	0.141	0.125	
PF4/L	-0.153	0.040	0.444	0.290	0.201	
PF5/L	1.680	1.385	1.852	2.157	1.161	
PF6/L	-1.741	-1.813	-1.434	-0.084	-0.079	
PF7/L	-0.457	-0.167	-0.189	-0.941	-1.292	
FPPC/L	0.000	0.000	0.000	0.000	0.000	
TF	0.034	0.034	0.034	0.034	0.034	
PLASMA	2.000	2.000	2.000	1.801	1.735	

TABLE 10.1-13 q=3 SN FLEXIBILITY POINTS [B=+4T]

	Lower SN
li, bN	0.4, 5.0	0.5, 2.2	0.7,0.0	1.2, 0.0	1.2, 5.0	
PF1/U	-1.518	-2.534	-3.000	-2.526	-1.883	
PF2/U	-2.271	-1.805	-0.717	-0.239	-0.358	
PF3/U	-0.597	-0.255	0.322	0.138	0.122	
PF4/U	-0.155	0.038	0.442	0.288	0.199	
PF5/U	1.699	1.404	1.871	2.176	1.180	
PF6/U	-1.714	-1.786	-1.407	-0.057	-0.052	
PF7/U	-0.457	-0.167	-0.189	-0.941	-1.292	
FPPC/U	0.000	0.000	0.000	0.000	0.000	
PF1/L	-1.518	-2.534	-3.000	-2.526	-1.883	
PF2/L	-2.271	-1.805	-0.717	-0.239	-0.358	
PF3/L	-0.951	-0.713	-0.165	0.379	0.054	
PF4/L	-0.791	-0.495	0.081	0.506	0.191	
PF5/L	3.366	3.130	3.378	2.612	2.582	
PF6/L	-2.172	-2.264	-1.834	-0.591	-0.571	
PF7/L	-0.457	-0.167	-0.189	-0.941	-1.292	
FPPC/L	0.000	0.000	0.000	0.000	0.000	
TF	-0.034	-0.034	-0.034	-0.034	-0.034	
PLASMA	2.000	2.000	2.000	1.801	1.714	

	Upper SN
li, bN	0.4, 5.0	0.5, 2.2	0.7,0.0	1.2, 0.0	1.2, 5.0	
PF1/U	-1.518	-2.534	-3.000	-2.526	-1.883	
PF2/U	-2.271	-1.805	-0.717	-0.239	-0.358	
PF3/U	-0.952	-0.714	-0.166	0.378	0.053	
PF4/U	-0.791	-0.495	0.081	0.506	0.191	
PF5/U	3.367	3.131	3.379	2.613	2.583	
PF6/U	-2.174	-2.266	-1.836	-0.593	-0.573	
PF7/U	-0.457	-0.167	-0.189	-0.941	-1.292	
FPPC/U	0.000	0.000	0.000	0.000	0.000	
PF1/L	-1.518	-2.534	-3.000	-2.526	-1.883	
PF2/L	-2.271	-1.805	-0.717	-0.239	-0.358	
PF3/L	-0.594	-0.252	0.325	0.141	0.125	
PF4/L	-0.153	0.040	0.444	0.290	0.201	
PF5/L	1.680	1.385	1.852	2.157	1.161	
PF6/L	-1.741	-1.813	-1.434	-0.084	-0.079	
PF7/L	-0.457	-0.167	-0.189	-0.941	-1.292	
FPPC/L	0.000	0.000	0.000	0.000	0.000	
TF	-0.034	-0.034	-0.034	-0.034	-0.034	
PLASMA	2.000	2.000	2.000	1.801	1.735	

TABLE 10.1-14 HC SCENARIO W/12V PLASMA INITIATION [B=-4T]

	Start of PF Current	Start of Loop Voltage (Pre-blip)	Plasma initiation	Start plasma control	End of Current Ramp - Start of Heating (SOF)	Start of Full Beta (SOB)	Start of Current Ramp-down (EOB)	End of Plasma Heating (EOC)	End of Plasma Current	End of PF Current	
Time (s)	-5.000	0.000	0.085	0.185	4.000	5.000	22.000	23.300	TBD	TBD	
Y0 (V-s)	0.000	9.000	8.220	7.280	-7.688	-8.000	-9.610	-7.300	TBD	TBD	
PF1/U	0.000	0.935	0.665	0.441	-3.173	-2.736	-2.962	-2.950	TBD	0.000	
PF2/U	0.000	2.317	2.058	2.292	-0.309	-0.197	-0.598	-0.220	TBD	0.000	
PF3/U	0.000	1.448	1.246	1.464	0.317	0.318	0.115	0.278	TBD	0.000	
PF4/U	0.000	1.406	1.225	0.994	0.477	0.463	0.265	0.363	TBD	0.000	
PF5/U	0.000	2.770	2.350	0.132	2.598	2.680	2.120	0.669	TBD	0.000	
PF6/U	0.000	0.144	0.103	0.067	-0.964	-0.588	-0.627	-0.135	TBD	0.000	
PF7/U	0.000	0.120	0.078	0.047	-0.720	-1.206	-1.215	-0.949	TBD	0.000	
FPPC/U	0.000	0.022	-0.017	-0.050	0.000	0.000	0.000	0.000	TBD	0.000	
PF1/L	0.000	0.935	0.665	0.441	-3.173	-2.736	-2.962	-2.950	TBD	0.000	
PF2/L	0.000	2.317	2.058	2.292	-0.309	-0.197	-0.598	-0.220	TBD	0.000	
PF3/L	0.000	1.448	1.246	1.464	0.313	0.314	0.111	0.274	TBD	0.000	
PF4/L	0.000	1.406	1.225	0.994	0.475	0.461	0.263	0.361	TBD	0.000	
PF5/L	0.000	2.770	2.350	0.132	2.618	2.700	2.140	0.689	TBD	0.000	
PF6/L	0.000	0.144	0.103	0.067	-0.939	-0.563	-0.602	-0.110	TBD	0.000	
PF7/L	0.000	0.120	0.078	0.047	-0.720	-1.206	-1.215	-0.949	TBD	0.000	
FPPC/L	0.000	0.022	-0.017	-0.050	0.000	0.000	0.000	0.000	0.000	0.000	
TF	0.034	0.034	0.034	0.034	0.034	0.034	0.034	0.034	0.034	0.034	
PLASMA			0.000	0.101	2.000	2.000	2.000	1.400	0.000		

TABLE 10.1-15 LC SCENARIO W/12V PLASMA INITIATION [B=-4T]

	Start of PF Current	Start of Loop Voltage (Pre-blip)	Plasma initiation	Start plasma control	400kA Plasma - Start of Heating (SOF)	400kA Plasma - Full Beta (SOB)	2MA Plasma - Full Beta - Start Current Ramp-down (EOB)	End of Plasma Heating (EOC)	End of Plasma Current	End of PF Current	
Time (s)	-5.000	0.000	0.085	0.185	2.000	3.000	36.500	37.500	TBD	TBD	
Y0 (V-s)	0.000	9.000	8.220	7.280	2.670	2.620	-9.020	-7.000	TBD	TBD	
PF1/U	0.000	0.935	0.665	0.441	-0.268	0.003	-2.656	-2.950	TBD	0.000	
PF2/U	0.000	2.317	2.058	2.292	1.180	1.115	-0.632	-0.220	TBD	0.000	
PF3/U	0.000	1.451	1.249	1.467	0.719	0.649	0.072	0.278	TBD	0.000	
PF4/U	0.000	1.408	1.227	0.996	0.720	0.648	0.235	0.363	TBD	0.000	
PF5/U	0.000	2.751	2.331	0.113	1.725	1.793	2.604	0.669	TBD	0.000	
PF6/U	0.000	0.117	0.076	0.040	0.150	0.215	-0.876	-0.135	TBD	0.000	
PF7/U	0.000	0.120	0.078	0.047	-0.294	-0.396	-1.044	-0.949	TBD	0.000	
FPPC/U	0.000	0.022	-0.017	-0.050	0.000	0.000	0.000	0.000	TBD	0.000	
PF1/L	0.000	0.935	0.665	0.441	-0.268	0.003	-2.656	-2.349	TBD	0.000	
PF2/L	0.000	2.317	2.058	2.292	1.180	1.115	-0.632	-0.526	TBD	0.000	
PF3/L	0.000	1.447	1.245	1.463	0.715	0.645	0.068	0.055	TBD	0.000	
PF4/L	0.000	1.406	1.225	0.994	0.718	0.646	0.233	0.173	TBD	0.000	
PF5/L	0.000	2.771	2.351	0.133	1.745	1.813	2.624	1.565	TBD	0.000	
PF6/L	0.000	0.142	0.101	0.065	0.175	0.240	-0.851	-0.718	TBD	0.000	
PF7/L	0.000	0.120	0.078	0.047	-0.294	-0.396	-1.044	-0.616	TBD	0.000	
FPPC/L	0.000	0.022	-0.017	-0.050	0.000	0.000	0.000	0.000	0.000	0.000	
TF	0.034	0.034	0.034	0.034	0.034	0.034	0.034	0.034	0.034	0.034	
PLASMA			0.000	0.101	0.400	0.400	2.000	1.450	0.000		

TABLE 10.1-16 20V PLASMA INITIATION [B=-4T]

	Start of PF Current	Start of Loop Voltage 
(Pre-blip)	Plasma initiation	Start plasma control	
Time (s)	-5.000	0.000	0.078	0.178	
Y0 (V-s)	0.000	0.000	0.000	0.000	
PF1/U	0.000	0.908	0.590	0.400	
PF2/U	0.000	2.189	1.686	1.233	
PF3/U	0.000	1.473	1.233	1.249	
PF4/U	0.000	1.449	1.145	1.426	
PF5/U	0.000	2.650	2.039	1.625	
PF6/U	0.000	0.095	0.045	0.043	
PF7/U	0.000	0.167	0.062	0.033	
FPPC/U	0.000	0.024	-0.037	-0.054	
PF1/L	0.000	0.908	0.590	0.400	
PF2/L	0.000	2.189	1.686	1.233	
PF3/L	0.000	1.469	1.229	1.245	
PF4/L	0.000	1.447	1.143	1.424	
PF5/L	0.000	2.670	2.059	1.645	
PF6/L	0.000	0.120	0.070	0.068	
PF7/L	0.000	0.167	0.062	0.033	
FPPC/L	0.000	0.024	-0.037	-0.054	
TF	0.034	0.034	0.034	0.034	
PLASMA			0.000	0.107	

TABLE 10.1-17 INBOARD PLASMA INITIATION [B=-4T]

[TBD]

TABLE 10.1-18 PLASMA INITIATION WITH RADIAL FIELD BIAS [B=-4T]

[TBD]

TABLE 10.1-19 PLASMA INITIATION WITH VERTICAL FIELD BIAS [B=-4T]

[TBD]

TABLE 10.1-20 3V PLASMA INITIATION [B=-4T]

[TBD]

TABLE 10.1-21 RADIAL POSITION CONTROL REQUIREMENTS FOR 20% DROPS IN PLASMA STORED ENERGY

[TBD]

TABLE 10.1-22 RADIAL POSITION CONTROL REQUIREMENTS FOR A 50% DROP IN PLASMA STORED ENERGY

[TBD]

TABLE 10.1-23 RADIAL POSITION CONTROL REQUIREMENTS FOR MOVING THE SEPARATRIX ±2CM IN 0.5S

[TBD]

TABLE 10.1-24 VERTICAL POSITION REQUIREMENTS FOR MOVING THE PLASMA ±TBD CM

[TBD]

TABLE 10.1-25 OUTBOARD STRIKE POINT POSITION CONTROL REQUIREMENTS FOR MOVING THE STRIKE POINT ±5CM

[TBD]