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STEP Fusion Power Plant

Hazard & Risk Analysis (HRA) — ISO/IEC/IEEE 15289 — Report | IEC 61508 Phase 3
Generated 2026-03-27 — UHT Journal / universalhex.org

Hazard Register

HazardSeverityFrequencySILSafe State
H-001: Plasma disruption — uncontrolled MHD instability dumps up to 1 GJ thermal energy onto first wall in <1ms, EM forces up to hundreds of MN critical high SIL 3 plasma terminated via massive gas injection, vessel integrity confirmed
H-002: Tritium release to environment — uncontrolled release of tritium (1-3 kg inventory) through double-barrier failure catastrophic rare SIL 3 building ventilation isolated, detritiation system activated
H-003: Superconducting magnet quench — loss of superconductivity in coils storing ~50 GJ, rapid helium boil-off critical low SIL 2 controlled fast discharge to dump resistors, cryogen vented via relief valves
H-004: Loss of coolant accident — rupture in cooling circuit, coolant ingress to vessel or loss of decay heat removal critical low SIL 2 plasma terminated, isolation valves closed, passive decay heat removal
H-005: Loss of vacuum — air ingress, exothermic beryllium-air reaction producing toxic/radioactive aerosol critical low SIL 2 plasma terminated, vessel isolation valves closed, containment filtered
H-006: Runaway electron beam — relativistic electrons >10 MeV from disruption current quench, localised first wall perforation critical medium SIL 3 beam dispersal via massive material injection
H-007: Activated dust explosion — beryllium/tungsten dust dispersed by air ingress exceeds explosive limit critical rare SIL 2 inert gas flood, air ingress sealed, dust inventory below threshold
H-008: Loss of cryogenic cooling — helium refrigeration failure causing whole-system magnet quench, asphyxiation risk critical low SIL 2 controlled magnet discharge, building ventilation maximum, evacuation
H-009: Seismic event — earthquake causing vessel/magnet displacement, simultaneous LOCA and quench catastrophic rare SIL 3 seismic trip, fast plasma shutdown, passive cooling
H-010: Neutron streaming — 14.1 MeV neutrons through penetrations exceed shielding, worker dose above limits major medium SIL 1 radiation interlocks, power reduced until shielding verified

SIL-Allocated Requirements

RefSILRequirementV&V
IFC-REQ-021 SIL 3 The interface between the Tritium Plant Plasma Exhaust Processing System and the Isotope Separation System SHALL transfer purified hydrogen isotopolog... Test
IFC-REQ-022 SIL 3 The interface between the Tritium Plant Isotope Separation System and the Tritium Storage and Delivery System SHALL transfer DT product at purity grea... Test
IFC-REQ-023 SIL 2 The interface between the Tritium Plant Blanket Tritium Extraction System and the Isotope Separation System SHALL transfer extracted tritium-in-helium... Test
IFC-REQ-024 SIL 2 The interface between the Superconducting Magnet System Quench Detection and Protection System and the Magnet Power Supply System SHALL transmit a har... Test
IFC-REQ-031 SIL 1 The interface between the In-Vessel Inspection and Maintenance Manipulator and the Remote Handling Control Suite SHALL use a real-time motion control ... Test
IFC-REQ-033 SIL 1 The interface between the In-Vessel Viewing and Monitoring System and the Remote Handling Control Suite SHALL deliver stereo video at ≥ 25 fps, ≥ 1080... Test
IFC-REQ-034 SIL 1 The interface between the Steam Generator and Heat Transfer System primary side and secondary side SHALL maintain tube-to-shell differential pressure ... Test
IFC-REQ-036 SIL 1 The interface between the Power Conversion System and the Plasma Control System SHALL receive plasma disruption notification within ≤ 100 ms of disrup... Test
SUB-REQ-001 SIL 3 The Plasma Control System SHALL execute the plasma position and shape control algorithm with a cycle time of 1 ms or less, processing all diagnostic i... Test
SUB-REQ-002 SIL 3 The Plasma Control System SHALL detect plasma disruption precursors (locked mode amplitude exceeding 5 mT, beta collapse rate exceeding 10%/ms, or n=1... Test
SUB-REQ-003 SIL 3 The Plasma Control System SHALL implement dual-redundant Real-Time Plasma Controllers executing identical algorithms in lockstep, with automatic switc... Test
SUB-REQ-004 SIL 3 The Plasma Control System Diagnostic Data Acquisition Front-End SHALL sample all 40 or more plasma diagnostic channels at a minimum rate of 1 kHz with... Test
SUB-REQ-005 SIL 3 When the Plasma Control System detects an internal fault (controller failure, loss of diagnostic data, or watchdog timeout), the Plasma Control System... Test
SUB-REQ-006 SIL 3 When a disruption current quench is detected, the Plasma Control System Disruption Prediction and Mitigation Unit SHALL trigger massive material injec... Test
SUB-REQ-015 SIL 3 The Tokamak Core Assembly Vacuum Vessel and In-Vessel Structures SHALL maintain plasma vessel leak rate below 1e-7 Pa m3/s total outgassing rate durin... Test
SUB-REQ-016 SIL 2 The Tokamak Core Assembly First Wall and Blanket Module SHALL achieve tritium breeding ratio (TBR) contribution of 1.1 or greater as measured from bla... Test
SUB-REQ-017 SIL 3 When a plasma disruption current quench is detected, the Tokamak Core Assembly SHALL withstand electromagnetic halo currents and induced eddy currents... Test
SUB-REQ-018 SIL 3 The Tritium Plant Plasma Exhaust Processing System SHALL process unburnt DT exhaust gas at a throughput of up to 200 Pa·m³/s, achieving hydrogen isoto... Test
SUB-REQ-019 SIL 3 The Tritium Plant Isotope Separation System SHALL produce DT fuel at a deuterium-tritium purity of greater than 99.9 mol% hydrogen isotopes and a D:T ... Test
SUB-REQ-020 SIL 3 The Tritium Plant Tritium Storage and Delivery System SHALL store tritium inventory in double-contained metal hydride beds with a maximum tritium hold... Test
SUB-REQ-021 SIL 2 The Tritium Plant Blanket Tritium Extraction System SHALL extract bred tritium from the lithium-ceramic blanket breeding zone at a rate matching the t... Test
SUB-REQ-022 SIL 3 When the Tritium Plant atmospheric tritium monitor detects a concentration exceeding 1e-5 Ci/m3 (1 MBq/m3), the Tritium Plant Atmosphere Detritiation ... Test
SUB-REQ-023 SIL 2 The Superconducting Magnet System Quench Detection and Protection System SHALL detect a resistive voltage signature greater than 100 mV on any superco... Test
SUB-REQ-024 SIL 2 The Superconducting Magnet System Central Solenoid SHALL provide a total flux swing of at least 100 V·s over a plasma pulse, with a maximum ramp rate ... Test
SUB-REQ-025 SIL 2 The Superconducting Magnet System TF Coil Set SHALL maintain a toroidal magnetic field of 3.2 T on plasma axis with a field ripple of less than 1% pea... Test
SUB-REQ-026 SIL 2 The Superconducting Magnet System Magnet Power Supply System SHALL energise the TF Coil Set to full field in less than 2 hours and the CS Coil to maxi... Test
SUB-REQ-027 SIL 2 When a quench interlock signal is received, the Superconducting Magnet System Magnet Power Supply System SHALL open all coil current loops and connect... Test
SUB-REQ-028 SIL 2 The Superconducting Magnet System TF Coil Set SHALL maintain superconducting operation at a winding-pack temperature of 4.5 K ± 0.1 K, with a minimum ... Test
SUB-REQ-031 SIL 2 The Cryogenic Plant Helium Refrigeration System SHALL provide minimum refrigeration capacity of 8 kW at 4.5 K per cold box train, with at least two in... Test
SUB-REQ-032 SIL 2 The Cryogenic Plant Helium Management System SHALL capture and recover not less than 95% of the helium gas released during a superconducting magnet qu... Test
SUB-REQ-033 SIL 2 The Cryogenic Plant Cryogenic Transfer Line Network SHALL maintain total static heat ingress to the 4.5 K helium circuit below 500 W across all transf... Test
SUB-REQ-034 SIL 2 The Cryogenic Plant Cryogenic Control System SHALL automatically execute the magnet cool-down sequence from 300 K to 4.5 K at a rate not exceeding 5 K... Test
SUB-REQ-035 SIL 2 When the Cryogenic Control System detects an internal fault (controller failure, loss of communication to >50% of sensors, or watchdog timeout), the C... Test
SUB-REQ-036 SIL 1 The Remote Handling System SHALL position the In-Vessel Inspection and Maintenance Manipulator end-effector to within ±1 mm of target coordinates in t... Test
SUB-REQ-037 SIL 1 The Remote Handling System SHALL complete a full blanket module exchange cycle (remove all 18 blanket modules, install replacement set) within 90 cale... Demonstration
SUB-REQ-038 SIL 1 The Remote Handling System SHALL maintain full functionality after cumulative absorbed dose of 1×10^6 Gy (gamma + neutron equivalent) at any in-vessel... Test
SUB-REQ-039 SIL 1 The Remote Handling Transfer Cask SHALL provide biological shielding such that dose rate at the cask outer surface does not exceed 2 mSv/hr when loade... Test
SUB-REQ-040 SIL 1 When any Remote Handling System equipment fault is detected (loss of position feedback, motor overcurrent, cable tension alarm), the Remote Handling S... Test
SUB-REQ-043 SIL 1 The Power Conversion System SHALL deliver electricity at 400 kV ± 5%, 50 Hz ± 0.5 Hz, with harmonic distortion < 3% THD, compliant with National Grid ... Test
SUB-REQ-045 SIL 1 When a plasma disruption is signalled by the Plasma Control System, the Power Conversion System SHALL execute a controlled turbine runback to 20% rate... Demonstration
SUB-REQ-073 SIL 1 The Remote Handling System SHALL implement a dual-path control architecture with independent main and backup control rooms, such that loss of the prim... Test
SUB-REQ-074 SIL 2 The Superconducting Magnet System Magnet Power Supply System SHALL implement N+1 redundancy for all AC/DC converter modules, such that loss of any sin... Test
SUB-REQ-075 SIL 2 The Vacuum System SHALL implement N+1 redundancy for all primary and backing pump trains on the torus and neutral beam injection lines, such that loss... Test
SUB-REQ-076 SIL 2 The Vacuum System SHALL qualify all torus vacuum vessel seals and penetration flanges to a leak rate of less than 1e-9 Pa m3/s per seal under all oper... Test
SUB-REQ-078 SIL 3 When a Design Basis Accident is declared, the Tritium Plant SHALL automatically isolate all tritium process and storage vessels within 30 seconds and ... Test
SUB-REQ-079 SIL 3 The Tokamak Core Assembly SHALL define and implement Design Basis Accident response for in-vessel component failure and loss-of-cooling events such th... Analysis
SUB-REQ-080 SIL 3 The Tritium Plant SHALL operate all tritium handling and storage activities under an approved Radiological Risk Assessment conforming to UK Ionising R... Inspection
SUB-REQ-081 SIL 2 The Vacuum System SHALL maintain plasma vessel seal integrity during all operational modes — including steady-state plasma burn, inter-shot vessel con... Test
SUB-REQ-083 SIL 3 The Tritium Plant SHALL implement N+1 process module redundancy for all active tritium processing stages — isotope separation, tritium purification, a... Test
SUB-REQ-084 SIL 2 The Superconducting Magnet System SHALL implement a passive quench energy absorption architecture such that failure of any single active quench detect... Analysis
SYS-REQ-007 SIL 2 The STEP Fusion Power Plant SHALL remove decay heat from in-vessel components passively (without active pumping) for at least 72 hours following loss ... Test
SYS-REQ-011 SIL 3 When ground acceleration exceeds 0.1g (OBE threshold), the STEP Fusion Power Plant SHALL initiate plasma shutdown within 100 ms of seismic trigger sig... Test
SYS-REQ-012 SIL 1 The STEP Fusion Power Plant SHALL limit neutron streaming through all penetrations such that dose rates in occupied areas remain below 10 µSv/hr durin... Test
SYS-REQ-018 SIL 3 The STEP Fusion Power Plant SHALL define a Design Basis Accident set encompassing at least: (a) maximum credible tritium release, (b) tokamak in-vesse... Analysis
VER-082 SIL 3 Verify SUB-REQ-078: On the Tritium Plant confinement test facility, simulate DBA tritium release by injecting a tracer gas at maximum credible leak ra... Test
VER-083 SIL 3 Verify SUB-REQ-079: Perform Design Basis Accident thermal analysis for loss-of-cooling to the Tokamak Core Assembly using the validated STEP thermal-h... Analysis
VER-084 SIL 3 Verify SUB-REQ-083: During Tritium Plant integrated commissioning at partial throughput, disable one active isotope separation module and measure trit... Test
VER-085 SIL 2 Verify SUB-REQ-084: Perform passive quench energy absorption analysis using the validated SMS electromagnetic and thermal model. Simulate single activ... Analysis
VER-088 SIL 2 Verify SUB-REQ-081: Following each plasma vessel maintenance intervention (seal replacement or penetration work), perform residual gas analysis measur... Test
VER-REQ-010 SIL 3 Verify SUB-REQ-001: Run the PCS control loop on the production hardware with all 40+ diagnostic channels active at 1 kHz injection rate. Instrument th... Test
VER-REQ-011 SIL 3 Verify SUB-REQ-002: Replay the full ITER/JET/MAST disruption database (at least 5000 disruptive events) through the PCS detection algorithm on hardwar... Test
VER-REQ-012 SIL 3 Verify SUB-REQ-005: In integrated commissioning, inject simulated controller fault signals (watchdog timeout, data loss, hardware alarm) while plasma ... Test
VER-REQ-013 SIL 3 Verify end-to-end plasma control: from disruption precursor signal injection at the Diagnostic Data Acquisition Front-End through the Real-Time Plasma... Test
VER-REQ-032 SIL 3 Verify IFC-REQ-017: With RHS deployed in port, assert PCS plasma-active interlock signal. Confirm RHS receives hardwired lockout and logs the event. P... Test
VER-REQ-036 SIL 3 Verify SUB-REQ-015: After full assembly, conduct helium leak test of vacuum vessel at 1e-8 Pa m3/s sensitivity. Additionally, perform hydrostatic over... Test
VER-REQ-038 SIL 3 Verify SUB-REQ-017: Run ANSYS electromagnetic analysis of worst-case disruption halo current (10 MA/m) on as-built TCA in-vessel structure FEM model. ... Test
VER-REQ-039 SIL 3 Verify SUB-REQ-018: Test PEPS on a full-scale prototype or equivalent test facility by injecting a calibrated DT+He mixture at 200 Pa m3/s. Measure se... Test
VER-REQ-040 SIL 3 Verify SUB-REQ-022: Inject a calibrated tritium tracer into the Atmosphere Detritiation System test facility atmosphere at 1e-5 Ci/m3. Confirm monitor... Test
VER-REQ-041 SIL 3 Verify IFC-REQ-021: During integrated commissioning, flow a simulated exhaust stream from PEPS to the ISS feed manifold. Sample the transfer line outl... Test
VER-REQ-042 SIL 3 Verify IFC-REQ-022: During fuel cycle commissioning, command an ISS batch product transfer to TSDS. Measure transfer latency from command to product r... Test
VER-REQ-043 SIL 3 Verify Tritium Plant end-to-end fuel cycle: During integrated commissioning at partial DT throughput (10% of full power equivalent), demonstrate conti... Demonstration
VER-REQ-044 SIL 2 Verify SUB-REQ-023: On a full-scale SMS test facility, inject a calibrated resistive heater into one coil segment simulating quench onset. Measure det... Test
VER-REQ-046 SIL 2 Verify SUB-REQ-027: Inject a simulated quench interlock signal and measure the time between signal injection and full opening of all coil current loop... Test
VER-REQ-054 SIL 2 Verify SUB-REQ-035: Inject a simulated PLC watchdog timeout fault in the production CCS hardware. Measure elapsed time from fault injection to: helium... Test
VER-REQ-058 SIL 1 Verify IFC-REQ-031: Test IVIMM-to-control-suite command interface latency using EtherCAT protocol analyser. Apply sinusoidal position command at 125 H... Test
VER-REQ-059 SIL 1 Verify IFC-REQ-032: Test cask-to-port docking interface on full-scale mockup using mass spectrometer helium leak test per ISO 20485. Leak rate pass cr... Test
VER-REQ-060 SIL 1 Verify IFC-REQ-033: Test in-vessel viewing system video delivery to control suite using network packet capture and hardware timestamp analysis. Measur... Test
VER-REQ-061 SIL 1 Verify IFC-REQ-034: Hydrostatically pressure-test each steam generator tube bundle at 1.5× design pressure (22.5 MPa) for 30 minutes per ASME Boiler a... Test
VER-REQ-063 SIL 1 Verify IFC-REQ-036: Test disruption notification interface by injecting test signal at PCS signal source and measuring time to turbine runback initiat... Test
VER-REQ-064 SIL 1 Verify SUB-REQ-036: Position IVIMM end-effector to 50 calibrated target positions distributed across the vessel workspace using laser tracker referenc... Test
VER-REQ-065 SIL 1 Verify SUB-REQ-041: During first full-power plasma commissioning run at Q≥5, measure net electrical power at 400 kV metering point (National Measureme... Demonstration
VER-REQ-066 SIL 1 Verify end-to-end Remote Handling System integration: conduct full blanket module exchange trial on vessel mockup at 1:1 scale, starting from operator... Demonstration
VER-REQ-067 SIL 1 Verify end-to-end Power Conversion System integration: during first plasma commissioning at Q≥5, measure complete energy chain from steam generator pr... Demonstration
VER-REQ-083 SIL 3 Verify IFC-REQ-023: During tritium plant commissioning, flow a representative tritium-in-helium mixture (0.1-1% T/He by volume) through the BTES-ISS t... Test
VER-REQ-084 SIL 3 Verify SUB-REQ-049: On the completed ISS installation, measure steady-state power consumption using calibrated three-phase power analyser at rated cry... Test
VER-REQ-085 SIL 3 Verify SUB-REQ-050: Assert the Plant Protection System emergency isolation command to the ISS via the hardwired interface. Measure time from command a... Test
VER-REQ-086 SIL 1 Verify SUB-REQ-051: Inspect the as-built turbine hall structure with a certified structural engineer. Confirm floor load rating certificate covers at ... Inspection
VER-REQ-087 SIL 3 Verify SUB-REQ-052: Conduct structural inspection of the as-built Tritium Plant confinement building. Confirm nuclear-grade seismic qualification cert... Inspection
VER-REQ-088 SIL 2 Verify SUB-REQ-053: Inspect the as-built Cryogenic Plant building. Measure insulated floor area using laser measurement system and confirm at least 80... Inspection
VER-REQ-089 SIL 2 Verify SUB-REQ-054: During vacuum system pre-commissioning, confirm by physical count and inspection that 12 turbomolecular pump assemblies are instal... Inspection
VER-REQ-090 SIL 3 Verify SYS-REQ-004: On the STEP Disruption Mitigation Test Bench, configure shattered pellet injection (SPI) system with representative pellet composi... Test
VER-REQ-091 SIL 3 Verify SYS-REQ-005: Perform integrated tritium containment integrity test across all Tritium Plant and in-vessel boundary segments. (1) Pressure-cycle... Test
VER-REQ-092 SIL 2 Verify SYS-REQ-006: On the STEP SMS full-scale quench protection test facility (or type-tested coil set representative of production magnets), inject ... Test
VER-REQ-093 SIL 2 Verify SYS-REQ-007: On the integrated passive decay heat removal test rig (full-scale replica of in-vessel cooling circuit with electrically-heated fi... Test
VER-REQ-094 SIL 3 Verify SYS-REQ-011: On the integrated Plant Protection System test bench, inject a simulated accelerometer signal exceeding 0.1g OBE threshold on all ... Test
VER-REQ-095 SIL 1 Verify SYS-REQ-012: On the as-built STEP facility at full-power plasma operation (minimum Q=5, ≥ 500 MWth fusion power), measure neutron and gamma dos... Test

Safety Case Structure (GSN)

Goal Structuring Notation per GSN Community Standard v3. Top goal decomposes into hazard mitigation sub-goals, each supported by SIL-allocated requirements and verification evidence.

flowchart TD
  G0["<b>G0: Top Goal</b><br/>STEP Fusion Power Plant is acceptably safe"]
  S0{"<b>S0: Strategy</b><br/>Argument by hazard<br/>mitigation per IEC 61508"}
  G0 --> S0
  G1["<b>G1: H-001</b><br/>Plasma disruption — uncontrolled MHD instability dumps up to...<br/>SIL 3"]
  S0 --> G1
  Sn0_0(["<b>SUB-REQ-002</b>"])
  G1 --> Sn0_0
  G2["<b>G2: H-002</b><br/>Tritium release to environment — uncontrolled release of tri...<br/>SIL 3"]
  S0 --> G2
  Sn1_0(["<b>VER-REQ-087</b>"])
  G2 --> Sn1_0
  G3["<b>G3: H-003</b><br/>Superconducting magnet quench — loss of superconductivity in...<br/>SIL 2"]
  S0 --> G3
  G4["<b>G4: H-004</b><br/>Loss of coolant accident — rupture in cooling circuit, coola...<br/>SIL 2"]
  S0 --> G4
  Sn3_0(["<b>SYS-REQ-007</b>"])
  G4 --> Sn3_0
  G5["<b>G5: H-005</b><br/>Loss of vacuum — air ingress, exothermic beryllium-air react...<br/>SIL 2"]
  S0 --> G5
  G6["<b>G6: H-006</b><br/>Runaway electron beam — relativistic electrons >10 MeV from ...<br/>SIL 3"]
  S0 --> G6
  Sn5_0(["<b>SUB-REQ-006</b>"])
  G6 --> Sn5_0
  G7["<b>G7: H-007</b><br/>Activated dust explosion — beryllium/tungsten dust dispersed...<br/>SIL 2"]
  S0 --> G7
  G8["<b>G8: H-008</b><br/>Loss of cryogenic cooling — helium refrigeration failure cau...<br/>SIL 2"]
  S0 --> G8
  G9["<b>G9: H-009</b><br/>Seismic event — earthquake causing vessel/magnet displacemen...<br/>SIL 3"]
  S0 --> G9
  G10["<b>G10: H-010</b><br/>Neutron streaming — 14.1 MeV neutrons through penetrations e...<br/>SIL 1"]
  S0 --> G10

GSN Export (YAML)

Machine-readable safety case structure. Import into GSN tools (Astah GSN, ASCE, NOR-STA).

# GSN Safety Case — STEP Fusion Power Plant
# Generated 2026-03-27
# Goal Structuring Notation (GSN) per GSN Community Standard v3

goals:
  G0:
    text: "STEP Fusion Power Plant is acceptably safe"
    type: top-goal
    supported_by: [S0]

strategies:
  S0:
    text: "Argument by hazard mitigation per IEC 61508"
    supported_by: [G1, G2, G3, G4, G5, G6, G7, G8, G9, G10]

  G1:
    text: "H-001: Plasma disruption — uncontrolled MHD instability dumps up to 1 GJ thermal energy onto first wall in <1ms, EM forces up to hundreds of MN"
    sil: 3
    safe_state: "plasma terminated via massive gas injection, vessel integrity confirmed"
    supported_by: [SUB-REQ-002]
    evidence: [VER-REQ-011, VER-REQ-011, VER-REQ-011]
  G2:
    text: "H-002: Tritium release to environment — uncontrolled release of tritium (1-3 kg inventory) through double-barrier failure"
    sil: 3
    safe_state: "building ventilation isolated, detritiation system activated"
    supported_by: [VER-REQ-087]
    evidence: []
  G3:
    text: "H-003: Superconducting magnet quench — loss of superconductivity in coils storing ~50 GJ, rapid helium boil-off"
    sil: 2
    safe_state: "controlled fast discharge to dump resistors, cryogen vented via relief valves"
    supported_by: []
    evidence: []
  G4:
    text: "H-004: Loss of coolant accident — rupture in cooling circuit, coolant ingress to vessel or loss of decay heat removal"
    sil: 2
    safe_state: "plasma terminated, isolation valves closed, passive decay heat removal"
    supported_by: [SYS-REQ-007]
    evidence: [VER-REQ-093, VER-REQ-093]
  G5:
    text: "H-005: Loss of vacuum — air ingress, exothermic beryllium-air reaction producing toxic/radioactive aerosol"
    sil: 2
    safe_state: "plasma terminated, vessel isolation valves closed, containment filtered"
    supported_by: []
    evidence: []
  G6:
    text: "H-006: Runaway electron beam — relativistic electrons >10 MeV from disruption current quench, localised first wall perforation"
    sil: 3
    safe_state: "beam dispersal via massive material injection"
    supported_by: [SUB-REQ-006]
    evidence: [REQ-SESTEPFUSIONPOWERPLANT-021, REQ-SESTEPFUSIONPOWERPLANT-021, REQ-SESTEPFUSIONPOWERPLANT-021]
  G7:
    text: "H-007: Activated dust explosion — beryllium/tungsten dust dispersed by air ingress exceeds explosive limit"
    sil: 2
    safe_state: "inert gas flood, air ingress sealed, dust inventory below threshold"
    supported_by: []
    evidence: []
  G8:
    text: "H-008: Loss of cryogenic cooling — helium refrigeration failure causing whole-system magnet quench, asphyxiation risk"
    sil: 2
    safe_state: "controlled magnet discharge, building ventilation maximum, evacuation"
    supported_by: []
    evidence: []
  G9:
    text: "H-009: Seismic event — earthquake causing vessel/magnet displacement, simultaneous LOCA and quench"
    sil: 3
    safe_state: "seismic trip, fast plasma shutdown, passive cooling"
    supported_by: []
    evidence: []
  G10:
    text: "H-010: Neutron streaming — 14.1 MeV neutrons through penetrations exceed shielding, worker dose above limits"
    sil: 1
    safe_state: "radiation interlocks, power reduced until shielding verified"
    supported_by: []
    evidence: []

solutions:
  IFC-REQ-021:
    text: "The interface between the Tritium Plant Plasma Exhaust Processing System and the Isotope Separation System SHALL transfe"
    verification: Test
    sil: 3
  IFC-REQ-022:
    text: "The interface between the Tritium Plant Isotope Separation System and the Tritium Storage and Delivery System SHALL tran"
    verification: Test
    sil: 3
  IFC-REQ-023:
    text: "The interface between the Tritium Plant Blanket Tritium Extraction System and the Isotope Separation System SHALL transf"
    verification: Test
    sil: 2
  IFC-REQ-024:
    text: "The interface between the Superconducting Magnet System Quench Detection and Protection System and the Magnet Power Supp"
    verification: Test
    sil: 2
  IFC-REQ-031:
    text: "The interface between the In-Vessel Inspection and Maintenance Manipulator and the Remote Handling Control Suite SHALL u"
    verification: Test
    sil: 1
  IFC-REQ-033:
    text: "The interface between the In-Vessel Viewing and Monitoring System and the Remote Handling Control Suite SHALL deliver st"
    verification: Test
    sil: 1
  IFC-REQ-034:
    text: "The interface between the Steam Generator and Heat Transfer System primary side and secondary side SHALL maintain tube-t"
    verification: Test
    sil: 1
  IFC-REQ-036:
    text: "The interface between the Power Conversion System and the Plasma Control System SHALL receive plasma disruption notifica"
    verification: Test
    sil: 1
  SUB-REQ-001:
    text: "The Plasma Control System SHALL execute the plasma position and shape control algorithm with a cycle time of 1 ms or les"
    verification: Test
    sil: 3
  SUB-REQ-002:
    text: "The Plasma Control System SHALL detect plasma disruption precursors (locked mode amplitude exceeding 5 mT, beta collapse"
    verification: Test
    sil: 3
  SUB-REQ-003:
    text: "The Plasma Control System SHALL implement dual-redundant Real-Time Plasma Controllers executing identical algorithms in "
    verification: Test
    sil: 3
  SUB-REQ-004:
    text: "The Plasma Control System Diagnostic Data Acquisition Front-End SHALL sample all 40 or more plasma diagnostic channels a"
    verification: Test
    sil: 3
  SUB-REQ-005:
    text: "When the Plasma Control System detects an internal fault (controller failure, loss of diagnostic data, or watchdog timeo"
    verification: Test
    sil: 3
  SUB-REQ-006:
    text: "When a disruption current quench is detected, the Plasma Control System Disruption Prediction and Mitigation Unit SHALL "
    verification: Test
    sil: 3
  SUB-REQ-015:
    text: "The Tokamak Core Assembly Vacuum Vessel and In-Vessel Structures SHALL maintain plasma vessel leak rate below 1e-7 Pa m3"
    verification: Test
    sil: 3
  SUB-REQ-016:
    text: "The Tokamak Core Assembly First Wall and Blanket Module SHALL achieve tritium breeding ratio (TBR) contribution of 1.1 o"
    verification: Test
    sil: 2
  SUB-REQ-017:
    text: "When a plasma disruption current quench is detected, the Tokamak Core Assembly SHALL withstand electromagnetic halo curr"
    verification: Test
    sil: 3
  SUB-REQ-018:
    text: "The Tritium Plant Plasma Exhaust Processing System SHALL process unburnt DT exhaust gas at a throughput of up to 200 Pa·"
    verification: Test
    sil: 3
  SUB-REQ-019:
    text: "The Tritium Plant Isotope Separation System SHALL produce DT fuel at a deuterium-tritium purity of greater than 99.9 mol"
    verification: Test
    sil: 3
  SUB-REQ-020:
    text: "The Tritium Plant Tritium Storage and Delivery System SHALL store tritium inventory in double-contained metal hydride be"
    verification: Test
    sil: 3
  SUB-REQ-021:
    text: "The Tritium Plant Blanket Tritium Extraction System SHALL extract bred tritium from the lithium-ceramic blanket breeding"
    verification: Test
    sil: 2
  SUB-REQ-022:
    text: "When the Tritium Plant atmospheric tritium monitor detects a concentration exceeding 1e-5 Ci/m3 (1 MBq/m3), the Tritium "
    verification: Test
    sil: 3
  SUB-REQ-023:
    text: "The Superconducting Magnet System Quench Detection and Protection System SHALL detect a resistive voltage signature grea"
    verification: Test
    sil: 2
  SUB-REQ-024:
    text: "The Superconducting Magnet System Central Solenoid SHALL provide a total flux swing of at least 100 V·s over a plasma pu"
    verification: Test
    sil: 2
  SUB-REQ-025:
    text: "The Superconducting Magnet System TF Coil Set SHALL maintain a toroidal magnetic field of 3.2 T on plasma axis with a fi"
    verification: Test
    sil: 2
  SUB-REQ-026:
    text: "The Superconducting Magnet System Magnet Power Supply System SHALL energise the TF Coil Set to full field in less than 2"
    verification: Test
    sil: 2
  SUB-REQ-027:
    text: "When a quench interlock signal is received, the Superconducting Magnet System Magnet Power Supply System SHALL open all "
    verification: Test
    sil: 2
  SUB-REQ-028:
    text: "The Superconducting Magnet System TF Coil Set SHALL maintain superconducting operation at a winding-pack temperature of "
    verification: Test
    sil: 2
  SUB-REQ-031:
    text: "The Cryogenic Plant Helium Refrigeration System SHALL provide minimum refrigeration capacity of 8 kW at 4.5 K per cold b"
    verification: Test
    sil: 2
  SUB-REQ-032:
    text: "The Cryogenic Plant Helium Management System SHALL capture and recover not less than 95% of the helium gas released duri"
    verification: Test
    sil: 2
  SUB-REQ-033:
    text: "The Cryogenic Plant Cryogenic Transfer Line Network SHALL maintain total static heat ingress to the 4.5 K helium circuit"
    verification: Test
    sil: 2
  SUB-REQ-034:
    text: "The Cryogenic Plant Cryogenic Control System SHALL automatically execute the magnet cool-down sequence from 300 K to 4.5"
    verification: Test
    sil: 2
  SUB-REQ-035:
    text: "When the Cryogenic Control System detects an internal fault (controller failure, loss of communication to >50% of sensor"
    verification: Test
    sil: 2
  SUB-REQ-036:
    text: "The Remote Handling System SHALL position the In-Vessel Inspection and Maintenance Manipulator end-effector to within ±1"
    verification: Test
    sil: 1
  SUB-REQ-037:
    text: "The Remote Handling System SHALL complete a full blanket module exchange cycle (remove all 18 blanket modules, install r"
    verification: Demonstration
    sil: 1
  SUB-REQ-038:
    text: "The Remote Handling System SHALL maintain full functionality after cumulative absorbed dose of 1×10^6 Gy (gamma + neutro"
    verification: Test
    sil: 1
  SUB-REQ-039:
    text: "The Remote Handling Transfer Cask SHALL provide biological shielding such that dose rate at the cask outer surface does "
    verification: Test
    sil: 1
  SUB-REQ-040:
    text: "When any Remote Handling System equipment fault is detected (loss of position feedback, motor overcurrent, cable tension"
    verification: Test
    sil: 1
  SUB-REQ-043:
    text: "The Power Conversion System SHALL deliver electricity at 400 kV ± 5%, 50 Hz ± 0.5 Hz, with harmonic distortion < 3% THD,"
    verification: Test
    sil: 1
  SUB-REQ-045:
    text: "When a plasma disruption is signalled by the Plasma Control System, the Power Conversion System SHALL execute a controll"
    verification: Demonstration
    sil: 1
  SUB-REQ-073:
    text: "The Remote Handling System SHALL implement a dual-path control architecture with independent main and backup control roo"
    verification: Test
    sil: 1
  SUB-REQ-074:
    text: "The Superconducting Magnet System Magnet Power Supply System SHALL implement N+1 redundancy for all AC/DC converter modu"
    verification: Test
    sil: 2
  SUB-REQ-075:
    text: "The Vacuum System SHALL implement N+1 redundancy for all primary and backing pump trains on the torus and neutral beam i"
    verification: Test
    sil: 2
  SUB-REQ-076:
    text: "The Vacuum System SHALL qualify all torus vacuum vessel seals and penetration flanges to a leak rate of less than 1e-9 P"
    verification: Test
    sil: 2
  SUB-REQ-078:
    text: "When a Design Basis Accident is declared, the Tritium Plant SHALL automatically isolate all tritium process and storage "
    verification: Test
    sil: 3
  SUB-REQ-079:
    text: "The Tokamak Core Assembly SHALL define and implement Design Basis Accident response for in-vessel component failure and "
    verification: Analysis
    sil: 3
  SUB-REQ-080:
    text: "The Tritium Plant SHALL operate all tritium handling and storage activities under an approved Radiological Risk Assessme"
    verification: Inspection
    sil: 3
  SUB-REQ-081:
    text: "The Vacuum System SHALL maintain plasma vessel seal integrity during all operational modes — including steady-state plas"
    verification: Test
    sil: 2
  SUB-REQ-083:
    text: "The Tritium Plant SHALL implement N+1 process module redundancy for all active tritium processing stages — isotope separ"
    verification: Test
    sil: 3
  SUB-REQ-084:
    text: "The Superconducting Magnet System SHALL implement a passive quench energy absorption architecture such that failure of a"
    verification: Analysis
    sil: 2
  SYS-REQ-007:
    text: "The STEP Fusion Power Plant SHALL remove decay heat from in-vessel components passively (without active pumping) for at "
    verification: Test
    sil: 2
  SYS-REQ-011:
    text: "When ground acceleration exceeds 0.1g (OBE threshold), the STEP Fusion Power Plant SHALL initiate plasma shutdown within"
    verification: Test
    sil: 3
  SYS-REQ-012:
    text: "The STEP Fusion Power Plant SHALL limit neutron streaming through all penetrations such that dose rates in occupied area"
    verification: Test
    sil: 1
  SYS-REQ-018:
    text: "The STEP Fusion Power Plant SHALL define a Design Basis Accident set encompassing at least: (a) maximum credible tritium"
    verification: Analysis
    sil: 3
  VER-082:
    text: "Verify SUB-REQ-078: On the Tritium Plant confinement test facility, simulate DBA tritium release by injecting a tracer g"
    verification: Test
    sil: 3
  VER-083:
    text: "Verify SUB-REQ-079: Perform Design Basis Accident thermal analysis for loss-of-cooling to the Tokamak Core Assembly usin"
    verification: Analysis
    sil: 3
  VER-084:
    text: "Verify SUB-REQ-083: During Tritium Plant integrated commissioning at partial throughput, disable one active isotope sepa"
    verification: Test
    sil: 3
  VER-085:
    text: "Verify SUB-REQ-084: Perform passive quench energy absorption analysis using the validated SMS electromagnetic and therma"
    verification: Analysis
    sil: 2
  VER-088:
    text: "Verify SUB-REQ-081: Following each plasma vessel maintenance intervention (seal replacement or penetration work), perfor"
    verification: Test
    sil: 2
  VER-REQ-010:
    text: "Verify SUB-REQ-001: Run the PCS control loop on the production hardware with all 40+ diagnostic channels active at 1 kHz"
    verification: Test
    sil: 3
  VER-REQ-011:
    text: "Verify SUB-REQ-002: Replay the full ITER/JET/MAST disruption database (at least 5000 disruptive events) through the PCS "
    verification: Test
    sil: 3
  VER-REQ-012:
    text: "Verify SUB-REQ-005: In integrated commissioning, inject simulated controller fault signals (watchdog timeout, data loss,"
    verification: Test
    sil: 3
  VER-REQ-013:
    text: "Verify end-to-end plasma control: from disruption precursor signal injection at the Diagnostic Data Acquisition Front-En"
    verification: Test
    sil: 3
  VER-REQ-032:
    text: "Verify IFC-REQ-017: With RHS deployed in port, assert PCS plasma-active interlock signal. Confirm RHS receives hardwired"
    verification: Test
    sil: 3
  VER-REQ-036:
    text: "Verify SUB-REQ-015: After full assembly, conduct helium leak test of vacuum vessel at 1e-8 Pa m3/s sensitivity. Addition"
    verification: Test
    sil: 3
  VER-REQ-038:
    text: "Verify SUB-REQ-017: Run ANSYS electromagnetic analysis of worst-case disruption halo current (10 MA/m) on as-built TCA i"
    verification: Test
    sil: 3
  VER-REQ-039:
    text: "Verify SUB-REQ-018: Test PEPS on a full-scale prototype or equivalent test facility by injecting a calibrated DT+He mixt"
    verification: Test
    sil: 3
  VER-REQ-040:
    text: "Verify SUB-REQ-022: Inject a calibrated tritium tracer into the Atmosphere Detritiation System test facility atmosphere "
    verification: Test
    sil: 3
  VER-REQ-041:
    text: "Verify IFC-REQ-021: During integrated commissioning, flow a simulated exhaust stream from PEPS to the ISS feed manifold."
    verification: Test
    sil: 3
  VER-REQ-042:
    text: "Verify IFC-REQ-022: During fuel cycle commissioning, command an ISS batch product transfer to TSDS. Measure transfer lat"
    verification: Test
    sil: 3
  VER-REQ-043:
    text: "Verify Tritium Plant end-to-end fuel cycle: During integrated commissioning at partial DT throughput (10% of full power "
    verification: Demonstration
    sil: 3
  VER-REQ-044:
    text: "Verify SUB-REQ-023: On a full-scale SMS test facility, inject a calibrated resistive heater into one coil segment simula"
    verification: Test
    sil: 2
  VER-REQ-046:
    text: "Verify SUB-REQ-027: Inject a simulated quench interlock signal and measure the time between signal injection and full op"
    verification: Test
    sil: 2
  VER-REQ-054:
    text: "Verify SUB-REQ-035: Inject a simulated PLC watchdog timeout fault in the production CCS hardware. Measure elapsed time f"
    verification: Test
    sil: 2
  VER-REQ-058:
    text: "Verify IFC-REQ-031: Test IVIMM-to-control-suite command interface latency using EtherCAT protocol analyser. Apply sinuso"
    verification: Test
    sil: 1
  VER-REQ-059:
    text: "Verify IFC-REQ-032: Test cask-to-port docking interface on full-scale mockup using mass spectrometer helium leak test pe"
    verification: Test
    sil: 1
  VER-REQ-060:
    text: "Verify IFC-REQ-033: Test in-vessel viewing system video delivery to control suite using network packet capture and hardw"
    verification: Test
    sil: 1
  VER-REQ-061:
    text: "Verify IFC-REQ-034: Hydrostatically pressure-test each steam generator tube bundle at 1.5× design pressure (22.5 MPa) fo"
    verification: Test
    sil: 1
  VER-REQ-063:
    text: "Verify IFC-REQ-036: Test disruption notification interface by injecting test signal at PCS signal source and measuring t"
    verification: Test
    sil: 1
  VER-REQ-064:
    text: "Verify SUB-REQ-036: Position IVIMM end-effector to 50 calibrated target positions distributed across the vessel workspac"
    verification: Test
    sil: 1
  VER-REQ-065:
    text: "Verify SUB-REQ-041: During first full-power plasma commissioning run at Q≥5, measure net electrical power at 400 kV mete"
    verification: Demonstration
    sil: 1
  VER-REQ-066:
    text: "Verify end-to-end Remote Handling System integration: conduct full blanket module exchange trial on vessel mockup at 1:1"
    verification: Demonstration
    sil: 1
  VER-REQ-067:
    text: "Verify end-to-end Power Conversion System integration: during first plasma commissioning at Q≥5, measure complete energy"
    verification: Demonstration
    sil: 1
  VER-REQ-083:
    text: "Verify IFC-REQ-023: During tritium plant commissioning, flow a representative tritium-in-helium mixture (0.1-1% T/He by "
    verification: Test
    sil: 3
  VER-REQ-084:
    text: "Verify SUB-REQ-049: On the completed ISS installation, measure steady-state power consumption using calibrated three-pha"
    verification: Test
    sil: 3
  VER-REQ-085:
    text: "Verify SUB-REQ-050: Assert the Plant Protection System emergency isolation command to the ISS via the hardwired interfac"
    verification: Test
    sil: 3
  VER-REQ-086:
    text: "Verify SUB-REQ-051: Inspect the as-built turbine hall structure with a certified structural engineer. Confirm floor load"
    verification: Inspection
    sil: 1
  VER-REQ-087:
    text: "Verify SUB-REQ-052: Conduct structural inspection of the as-built Tritium Plant confinement building. Confirm nuclear-gr"
    verification: Inspection
    sil: 3
  VER-REQ-088:
    text: "Verify SUB-REQ-053: Inspect the as-built Cryogenic Plant building. Measure insulated floor area using laser measurement "
    verification: Inspection
    sil: 2
  VER-REQ-089:
    text: "Verify SUB-REQ-054: During vacuum system pre-commissioning, confirm by physical count and inspection that 12 turbomolecu"
    verification: Inspection
    sil: 2
  VER-REQ-090:
    text: "Verify SYS-REQ-004: On the STEP Disruption Mitigation Test Bench, configure shattered pellet injection (SPI) system with"
    verification: Test
    sil: 3
  VER-REQ-091:
    text: "Verify SYS-REQ-005: Perform integrated tritium containment integrity test across all Tritium Plant and in-vessel boundar"
    verification: Test
    sil: 3
  VER-REQ-092:
    text: "Verify SYS-REQ-006: On the STEP SMS full-scale quench protection test facility (or type-tested coil set representative o"
    verification: Test
    sil: 2
  VER-REQ-093:
    text: "Verify SYS-REQ-007: On the integrated passive decay heat removal test rig (full-scale replica of in-vessel cooling circu"
    verification: Test
    sil: 2
  VER-REQ-094:
    text: "Verify SYS-REQ-011: On the integrated Plant Protection System test bench, inject a simulated accelerometer signal exceed"
    verification: Test
    sil: 3
  VER-REQ-095:
    text: "Verify SYS-REQ-012: On the as-built STEP facility at full-power plasma operation (minimum Q=5, ≥ 500 MWth fusion power),"
    verification: Test
    sil: 1