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STEP Fusion Power Plant

System Requirements Specification (SyRS) — ISO/IEC/IEEE 15289 — Specification | IEEE 29148 §6.2–6.4
Generated 2026-03-27 — UHT Journal / universalhex.org

Referenced Standards

StandardTitle
BS EN 61000-3
EN 61000-2-4
IEC 60034-1
IEC 60076-1
IEC 60364
IEC 61000-4-30 Electromagnetic compatibility — Radiated, radio-frequency, electromagnetic field immunity test
IEC 61000-4-7
IEC 61508 Functional safety of electrical/electronic/programmable electronic safety-related systems
IEC 61511 Functional safety — Safety instrumented systems for the process industry sector
IEC 61513 Nuclear power plants — Instrumentation and control important to safety
IEC 61850
IEC 62061 Safety of machinery — Functional safety of safety-related control systems
ISO 14001
ISO 14577
ISO 20485
ISO 29148
ISO 2919

Acronyms & Abbreviations

AcronymExpansion
ALARA As Low As Reasonably Achievable
ARC Architecture Decisions
CCCS Completeness, Consistency, Correctness, Stability
CUSC System Code
EARS Easy Approach to Requirements Syntax
IFC Interface Requirements
LOCA Coolant Accident
OBE Operational Basis Earthquake
ONR Nuclear Safety Regulator
SSE Safe Shutdown Earthquake
STK Stakeholder Requirements
SUB Subsystem Requirements
SYS System Requirements
UHT Universal Hex Taxonomy
VER Verification Plan

Stakeholder Requirements (STK)

RefRequirementV&VTags
STK-REQ-001 The STEP Fusion Power Plant SHALL provide the control room operator with real-time plasma state displays updating at ≥10 Hz, including plasma current, stored energy, density, and MHD stability indicators.
Rationale: Control Room Operator, S-001 Full-Power Burn: operators must continuously monitor plasma parameters during 6-hour burn pulses to detect instabilities and decide on intervention timing.
Demonstration stakeholder, stk-operator, session-506, idempotency:stk-operator-display-506
STK-REQ-002 The STEP Fusion Power Plant SHALL enable operator-initiated emergency plasma termination within 2 operator actions and ≤5 seconds from decision to actuation.
Rationale: test update
Demonstration stakeholder, stk-operator, session-506, idempotency:stk-operator-emergency-506
STK-REQ-003 The STEP Fusion Power Plant SHALL demonstrate a deterministic nuclear safety case compliant with ONR Safety Assessment Principles, including fault analysis for all Design Basis Accidents with consequences below ONR Basic Safety Levels.
Rationale: Nuclear Safety Regulator (ONR), all scenarios: ONR must license the first fusion nuclear facility; the safety case must meet established nuclear standards adapted for fusion-specific hazards.
Analysis stakeholder, stk-onr, session-506, idempotency:stk-onr-safetycase-506
STK-REQ-004 The STEP Fusion Power Plant SHALL maintain tritium inventory accountability to ±0.1 g precision and provide real-time tritium balance reporting to the regulator.
Rationale: Nuclear Safety Regulator (ONR), S-003 Tritium Processing Malfunction: tritium is the principal nuclear material; loss-of-accountability triggers regulatory escalation and potential licence conditions.
Test stakeholder, stk-onr, session-506, idempotency:stk-onr-tritium-accountability-506
STK-REQ-005 The STEP Fusion Power Plant SHALL provide remote handling capability to replace all in-vessel components (divertor cassettes, blanket modules, diagnostics) without human entry to activated areas.
Rationale: Remote Handling Engineer, S-005 Planned Maintenance: in-vessel dose rates exceed 10 Sv/hr post-operation, making human entry impossible; all maintenance must be robotic with hot cell support.
Demonstration stakeholder, stk-remote-handling, session-506, idempotency:stk-rh-capability-506
STK-REQ-006 The STEP Fusion Power Plant SHALL complete a full divertor cassette replacement campaign (8 cassettes) within 4 months using remote handling systems.
Rationale: Remote Handling Engineer, S-005 Planned Maintenance: 4-month maintenance campaign target drives plant availability to 50%; exceeding this timeline directly reduces energy output and economic viability.
Demonstration stakeholder, stk-remote-handling, session-506, idempotency:stk-rh-campaign-506
STK-REQ-007 The STEP Fusion Power Plant SHALL operate a closed tritium fuel cycle with breeding ratio TBR ≥ 1.1, processing exhaust gas to recover unburned tritium within 4 hours of extraction.
Rationale: Tritium Plant Operator, S-001 Full-Power Burn: tritium self-sufficiency is a fundamental mission requirement; external tritium supply is limited and expensive, so breeding and recycling must close the loop.
Test stakeholder, stk-tritium-operator, session-506, idempotency:stk-tritium-fuelcycle-506
STK-REQ-008 When a tritium system leak is detected, the STEP Fusion Power Plant SHALL automatically isolate the affected line within 30 seconds and activate secondary containment.
Rationale: Tritium Plant Operator, S-003 Tritium Processing Malfunction: automatic isolation prevents inventory loss and environmental release; 30s threshold limits release to <0.1 g per scenario analysis.
Test stakeholder, stk-tritium-operator, session-506, idempotency:stk-tritium-isolation-506
STK-REQ-009 The STEP Fusion Power Plant SHALL deliver net electrical power of ≥100 MW to the 400 kV grid connection point during steady-state burn, compliant with National Grid ESO Grid Code for frequency response and voltage regulation.
Rationale: Grid Transmission Operator (National Grid ESO), S-001 Full-Power Burn: the fundamental mission of STEP is to demonstrate net electricity generation; Grid Code compliance is mandatory for grid connection.
Test stakeholder, stk-grid-operator, session-506, idempotency:stk-grid-power-506
STK-REQ-010 The STEP Fusion Power Plant SHALL provide 24-hour advance notification to National Grid ESO of planned pulse schedules and ≥15 minutes warning of unplanned shutdowns.
Rationale: Grid Transmission Operator (National Grid ESO), S-001/S-004: pulsed power profile requires grid scheduling; unplanned loss of 100 MW generation affects grid stability.
Demonstration stakeholder, stk-grid-operator, session-506, idempotency:stk-grid-notification-506
STK-REQ-011 The STEP Fusion Power Plant SHALL maintain individual worker radiation doses below 20 mSv/year with an ALARP target of <1 mSv/year, through shielding, remote operations, and access controls.
Rationale: Radiation Protection Adviser, S-005/S-004: IRR17 dose limits and ALARP principle are non-negotiable regulatory requirements; 14.1 MeV neutron environment and activation make dose management critical.
Analysis stakeholder, stk-rpa, session-506, idempotency:stk-rpa-dose-506
STK-REQ-012 The STEP Fusion Power Plant SHALL classify all areas by radiation zone and enforce interlocked access controls preventing entry to zones exceeding the worker's authorised dose rate.
Rationale: Radiation Protection Adviser, S-005 Planned Maintenance: maintenance campaigns involve variable dose rates across the facility; automated zoning prevents inadvertent exposure during complex multi-team operations.
Inspection stakeholder, stk-rpa, session-506, idempotency:stk-rpa-zoning-506
STK-REQ-013 The STEP Fusion Power Plant SHALL limit all radioactive discharges (gaseous and liquid) to levels below Environmental Permitting Regulations limits, with continuous stack and effluent monitoring.
Rationale: Environment Agency: EPR compliance is a condition of operation; continuous monitoring provides the evidence base for the environmental safety case and public dose assessment.
Test stakeholder, stk-environment-agency, session-506, idempotency:stk-ea-discharges-506
STK-REQ-014 The STEP Fusion Power Plant SHALL categorise all radioactive waste at source and provide interim storage for ILW with a 100-year design life pending national disposal facility availability.
Rationale: Environment Agency: no UK geological disposal facility exists yet for ILW; the plant must demonstrate a credible waste strategy with long-duration interim storage to obtain environmental permits.
Inspection stakeholder, stk-environment-agency, session-506, idempotency:stk-ea-waste-506
STK-REQ-015 The STEP Fusion Power Plant SHALL maintain off-site radiation doses below 1 mSv/year to any member of the public, including contributions from routine discharges, direct radiation, and accident scenarios.
Rationale: Local Community and Public: public dose limit under IRR17; community acceptance depends on demonstrating that fusion is radiologically safe under all conditions including accidents.
Analysis stakeholder, stk-public, session-506, idempotency:stk-public-dose-506
STK-REQ-016 The STEP Fusion Power Plant SHALL implement an emergency planning zone with public notification capability achieving ≥95% population coverage within 15 minutes of a declared nuclear emergency.
Rationale: Local Community and Public, S-003/S-004: REPPIR regulations require off-site emergency planning; rapid notification is essential for public protection during tritium release or seismic events.
Demonstration stakeholder, stk-public, session-506, idempotency:stk-public-emergency-506
STK-REQ-017 The STEP Fusion Power Plant SHALL provide comprehensive plasma physics diagnostic data (≥40 diagnostic systems) with calibrated, time-synchronised output available to the fusion research community within 30 days of each campaign.
Rationale: Fusion Research Community (UKAEA, EUROfusion): STEP's dual mission includes advancing fusion science; diagnostic data validates physics models and informs DEMO/commercial reactor design.
Demonstration stakeholder, stk-research, session-506, idempotency:stk-research-diagnostics-506
STK-REQ-018 The STEP Fusion Power Plant SHALL validate tritium breeding blanket performance through in-situ measurement of tritium production rates, neutron spectra, and thermal-hydraulic conditions in breeding modules.
Rationale: Fusion Research Community (UKAEA, EUROfusion), S-001: breeding blanket validation is a key STEP mission deliverable; no prior device has operated a breeding blanket in a DT neutron environment at reactor scale.
Test stakeholder, stk-research, session-506, idempotency:stk-research-blanket-506
STK-REQ-019 The STEP Fusion Power Plant SHALL be designed for decommissioning with all components classifiable under UK radioactive waste categories, and a demonstrated dismantling sequence achievable within 30 years of final shutdown.
Rationale: Decommissioning Authority: NDA and ONR require a credible decommissioning strategy at the design stage; 30-year timeline aligns with UK nuclear decommissioning practice and funding models.
Analysis stakeholder, stk-decommissioning, session-506, idempotency:stk-decom-timeline-506
STK-REQ-020 The STEP Fusion Power Plant SHALL minimise activation of structural materials through material selection (reduced-activation steels, tungsten, SiC composites) such that ≥80% of decommissioning waste is classifiable as LLW within 100 years.
Rationale: Decommissioning Authority: minimising ILW reduces long-term storage burden and cost; material choice at design stage is the primary lever for waste classification outcomes.
Analysis stakeholder, stk-decommissioning, session-506, idempotency:stk-decom-materials-506

System Requirements (SYS)

RefRequirementV&VTags
SYS-REQ-001 The STEP Fusion Power Plant SHALL sustain deuterium-tritium plasma burn at fusion gain Q ≥ 5 for pulse durations of 2 to 8 hours with plasma current ≥ 10 MA.
Rationale: Derives from STK-REQ-009 (net 100 MW to grid) and mission statement. Q≥5 is the minimum gain to produce ~500 MW fusion power from ~100 MW auxiliary heating, yielding ~100 MW net after recirculating power. Pulse duration drives energy yield per campaign.
Test system, plasma, session-506, idempotency:sys-plasma-burn-506
SYS-REQ-002 The STEP Fusion Power Plant SHALL convert fusion thermal power to net electrical output of ≥ 100 MW at the 400 kV grid connection point with a gross-to-net efficiency ≥ 25%.
Rationale: Derives from STK-REQ-009. ~500 MW fusion thermal power requires ~33% gross thermal efficiency to yield ~165 MW gross; after ~65 MW recirculating power for magnets, heating, and auxiliaries, ≥100 MW net is delivered. 25% gross-to-net accounts for all parasitic loads.
Test system, power, session-506, idempotency:sys-power-conversion-506
SYS-REQ-003 The STEP Fusion Power Plant SHALL achieve a tritium breeding ratio (TBR) ≥ 1.1 measured across the breeding blanket, producing net bred tritium at a rate exceeding DT fuel consumption by ≥ 10% to accumulate a reserve inventory of ≥ 1 kg tritium within 12 months of full-power operation.
Rationale: TBR ≥ 1.1 means 10% excess production over consumption rate. At planned 500 MW fusion power with 50% availability, annual DT consumption is ~4 kg T; 10% surplus yields ~400 g/year reserve accumulation, reaching ≥1 kg within 3 years. The 1 kg reserve provides 2-3 month fuel buffer against breeding blanket underperformance. The original text said 'sufficient tritium' which is non-measurable; this revision specifies both the rate and target inventory. Revised in validation session 519 to address AmbiguityBlacklist finding.
Test system, tritium, session-506, idempotency:sys-tbr-506
SYS-REQ-004 When a plasma disruption is detected, the STEP Fusion Power Plant SHALL initiate disruption mitigation (shattered pellet injection or massive gas injection) within 10 ms and limit thermal loads on the first wall to ≤ 0.5 MJ/m².
Rationale: Derives from STK-REQ-002, addresses H-001 (SIL 3). 10 ms response time is driven by thermal quench timescale of ~1 ms; mitigation must be initiated during the pre-thermal-quench phase. 0.5 MJ/m² is the tungsten damage threshold for single events.
Test rt-resolved-session-531
SYS-REQ-005 The STEP Fusion Power Plant SHALL confine all tritium within at least two independent containment barriers under nominal operating, anticipated transient, and design basis accident conditions, limiting any single-event release to < 0.1 g tritium.
Rationale: Derives from STK-REQ-001 and STK-REQ-003, addresses H-002 (SIL-3 tritium release). 0.1 g single-event limit derives from UK nuclear site licence conditions and ONR regulatory guides for fusion: at this inventory level, atmospheric dispersion models show ground-level concentration at the site boundary remains below 1% of the occupational exposure limit. Two-barrier requirement derives from nuclear containment principles. 'Nominal operating, anticipated transient, and design basis accident' replaces ambiguous 'normal' to comply with ISO 29148 unambiguous language requirement; updated validation session 520.
Test rt-resolved-session-531
SYS-REQ-006 The STEP Fusion Power Plant SHALL detect and safely manage superconducting magnet quench events by discharging stored magnetic energy (up to 50 GJ) to dump resistors within 30 seconds, limiting hot-spot temperature to < 300 K.
Rationale: Derives from STK-REQ-003, addresses H-003 (SIL 2). 50 GJ stored energy in HTS magnets must be extracted before conductor damage occurs; 300 K hot-spot limit prevents irreversible degradation of HTS tape. 30s discharge time balances voltage limits against thermal margin.
Test rt-resolved-session-531
SYS-REQ-007 The STEP Fusion Power Plant SHALL remove decay heat from in-vessel components passively (without active pumping) for at least 72 hours following loss of all AC power, maintaining structural temperatures below design limits.
Rationale: Passive decay heat removal is safety-critical (SIL-2, hazard H-004 LOCA). VER-REQ-093 specifies physical Test on a full-scale passive decay heat removal test rig. Analysis alone cannot account for as-built thermal resistance, fouling, or water chemistry effects on natural circulation. IEC 61508 SIL-2 requires Test verification for this failure mode. Changed from Analysis to Test in validation session 520 to resolve quality gate blocker.
Test system, safety, sil-2, session-506, idempotency:sys-passive-decay-heat-506
SYS-REQ-008 The STEP Fusion Power Plant SHALL maintain ultra-high vacuum (< 1×10⁻⁶ Pa) in the plasma vessel with a total leak rate < 1×10⁻⁹ Pa·m³/s per seal during all operational modes.
Rationale: Derives from vacuum constraints and STK-REQ-001 (plasma operation). Impurity ingress from leaks poisons the plasma and triggers disruptions; 1e-6 Pa base pressure is required for plasma breakdown and burn purity.
Test system, vacuum, session-506, idempotency:sys-vacuum-506
SYS-REQ-009 The STEP Fusion Power Plant SHALL provide a remote handling system capable of replacing all in-vessel components within a 4-month maintenance campaign, with component positioning accuracy ≤ 2 mm.
Rationale: Derives from STK-REQ-005, STK-REQ-006. 4-month campaign duration drives 50% plant availability target. 2 mm positioning accuracy is required for divertor cassette alignment to magnetic field geometry and coolant seal engagement.
Demonstration system, remote-handling, session-506, idempotency:sys-remote-handling-506
SYS-REQ-010 The STEP Fusion Power Plant SHALL achieve ≥ 50% operational availability over a 6-month campaign, defined as burn-hours divided by calendar-hours excluding planned maintenance.
Rationale: Derives from STK-REQ-009 and operational tempo constraint. 50% availability with 100 MW net output yields ~440 GWh per year, demonstrating economic relevance. Availability is limited by inter-pulse turnaround (30 min–4 hr) and unplanned downtime.
Analysis system, performance, session-506, idempotency:sys-availability-506
SYS-REQ-011 When ground acceleration exceeds 0.1g (OBE threshold), the STEP Fusion Power Plant SHALL initiate plasma shutdown within 100 ms of seismic trigger signal receipt and transition all subsystems to seismically-safe states within 10 seconds.
Rationale: SIL-3 seismic trip requirement. 100 ms shutdown window is set by maximum halo current exposure duration before structural damage to in-vessel components; beyond 100 ms, asymmetric disruption loads exceed design basis. 10 second full subsystem safe-state transition covers magnet hold current reduction, tritium confinement isolation, and vacuum system standby mode. Removed the adjective 'fast' (ambiguous) as the 100 ms bound is self-defining; added explicit 10-second subsystem transition bound absent from original. Revised in validation session 519.
Test system, safety, sil-3, session-506, idempotency:sys-seismic-trip-506
SYS-REQ-012 The STEP Fusion Power Plant SHALL limit neutron streaming through all penetrations such that dose rates in occupied areas remain below 10 µSv/hr during full-power operation.
Rationale: Neutron streaming dose rate must be measured in-situ at full-power operation; MCNP analysis cannot fully account for as-built penetration tolerances, cable routing gaps, and local shielding variations. VER-REQ-095 specifies calibrated dosimetry measurement at all occupied area boundaries during full-power plasma. Changed from Analysis to Test in validation session 520 to resolve quality gate blocker and meet IEC 61508 SIL-1 requirements for occupied area radiation protection.
Test system, safety, sil-1, session-506, idempotency:sys-neutron-shielding-506
SYS-REQ-013 The STEP Fusion Power Plant SHALL provide ≥ 40 plasma diagnostic systems with calibrated, time-synchronised measurements (timing accuracy ≤ 1 µs) covering magnetic, kinetic, and spectroscopic parameters.
Rationale: Derives from STK-REQ-017. 40 diagnostic systems is the minimum for comprehensive plasma characterisation of a burning DT plasma; 1 µs synchronisation enables correlation of fast MHD events across diagnostic channels.
Demonstration system, diagnostics, session-506, idempotency:sys-diagnostics-506
SYS-REQ-014 The STEP Fusion Power Plant SHALL be designed such that ≥ 80% of decommissioning waste by volume is classifiable as LLW within 100 years of final shutdown through use of reduced-activation materials.
Rationale: Derives from STK-REQ-019, STK-REQ-020. Reduced-activation ferritic-martensitic steels (e.g., EUROFER) and tungsten selection at design stage determines activation products and decay timescales. 80% LLW target minimises ILW storage burden.
Analysis system, decommissioning, session-506, idempotency:sys-decom-waste-506
SYS-REQ-015 The STEP Fusion Power Plant SHALL comply with Grid Code requirements for power quality, delivering electricity at 400 kV ± 5%, 50 Hz ± 0.5 Hz, with harmonic distortion < 3% THD.
Rationale: Derives from STK-REQ-009. Grid Code compliance is mandatory for connection; voltage and frequency tolerances are National Grid ESO standard requirements; THD limit prevents interference with other grid users.
Test system, power, session-506, idempotency:sys-grid-quality-506
SYS-REQ-016 The STEP Fusion Power Plant SHALL implement radiobiological protection measures such that occupational whole-body dose to any worker does not exceed 1 mSv/year above background in designated supervised areas, and the plant SHALL maintain ALARA (As Low As Reasonably Achievable) dose management in accordance with UK IRR 2017 and ONR nuclear site licence conditions, documented in an approved Radiation Protection Supervisors programme.
Rationale: A fusion power plant generates neutron activation products and tritium, creating radiobiological hazards to workers and the public. UK law requires compliance with IRR 2017 and ONR site licence conditions. The 1 mSv/year limit (above background) is the HSE-recommended constraint for designated areas at nuclear facilities. This requirement flows from STK-REQ-003 (safety assessment principles), STK-REQ-004 (tritium accountability), and the Biological/Biomimetic ontological trait assigned to the STEP system entity reflecting biological dose considerations.
Analysis idempotency:sys-radiobio-protection-516
SYS-REQ-017 The STEP Fusion Power Plant SHALL provide 24-hour advance notification to National Grid of planned generation schedule changes exceeding 10 MW, and SHALL notify within 15 minutes of any unplanned generation interruption affecting grid frequency response obligations.
Rationale: STK-REQ-010 mandates 24-hour advance notification; no SYS requirement currently implements this stakeholder need. UK Grid Code CC.6.3.2 requires mandatory advance notice for scheduled plant outages. The 15-minute unplanned interruption notification is derived from National Grid's Balancing and Settlement Code and Grid Code requirements for frequency response obligations: a delay beyond 15 minutes may trigger Grid Code non-compliance penalties and affect National Grid's ability to dispatch balancing mechanisms.
Demonstration system, grid, grid-code, session-552, idempotency:sys-grid-notification-24h-552
SYS-REQ-018 The STEP Fusion Power Plant SHALL define a Design Basis Accident set encompassing at least: (a) maximum credible tritium release, (b) tokamak in-vessel component failure with delayed ex-vessel rupture, (c) superconducting magnet quench cascade, and (d) loss-of-cooling to decay heat removal system; and SHALL demonstrate in the Nuclear Safety Case that each DBA does not exceed the Basic Safety Level dose limits of 1 mSv effective dose to any member of the public.
Rationale: STK-REQ-003 requires demonstration of a deterministic nuclear safety case using Design Basis Accidents and basic safety levels; no SYS requirement currently decomposes this. The four DBA categories represent the STEP-specific risk inventory: tritium release is the primary radiological source term; in-vessel component failure is the primary structural hazard; magnet quench cascade is the primary energy release event; and loss of decay heat cooling is the primary post-shutdown hazard. The 1 mSv DBA dose limit is derived from IAEA SSR-2/1 and ONR technical assessment guide NS-TAST-GD-005 for near-field nuclear installations.
Analysis system, safety, sil-3, dba, session-552, idempotency:sys-dba-basic-safety-level-552
SYS-REQ-019 The STEP Fusion Power Plant SHALL obtain and maintain all required environmental permits under the Environmental Permitting (England and Wales) Regulations 2016 and the Nuclear Installations Act 1965, and SHALL demonstrate continuous compliance by maintaining a certified Environmental Management System conforming to ISO 14001 with annual third-party audit.
Rationale: STK-REQ-013 mandates compliance with environmental permitting regulations; no SYS requirement currently implements this. Environmental Permitting (England and Wales) Regulations 2016 apply to all nuclear sites discharging radioactive substances to the environment; compliance is a condition of the ONR nuclear site licence. ISO 14001 certification provides an independent, internationally recognised framework for ongoing environmental compliance management. Annual third-party audit is the minimum frequency required by ONR guidance for nuclear site environmental management systems.
Inspection system, environmental, regulatory, session-552, idempotency:sys-env-permitting-iso14001-552
SYS-REQ-020 The STEP Fusion Power Plant SHALL publish processed plasma physics diagnostic data to the fusion research community data repository within 30 days of each experimental campaign completion, in conformance with FAIR data principles (Findable, Accessible, Interoperable, Reusable).
Rationale: STK-REQ-017 mandates data sharing within 30 days; no SYS requirement implements this. STEP is a publicly funded programme with open-science obligations under UKRI data management policy. The 30-day window is the STK-stated constraint derived from the UK Research and Innovation open data requirements for nationally significant science infrastructure. FAIR data principles are the international standard for scientific data interoperability, adopted by EUROfusion and mandatory for fusion science facilities receiving EU/UK public funding.
Inspection system, research, data, session-552, idempotency:sys-research-data-30days-552

Requirements by Category (IEEE 29148)

4
Functional Requirements
16
Performance Requirements
1
Safety Requirements
4
Environmental Requirements
1
Reliability & Availability
3
Compliance & Regulatory
2
Other

Traceability Matrix — STK to SYS

SourceTargetTypeDescription
STK-REQ-017 SYS-REQ-020 derives STK research data sharing → SYS FAIR data publication requirement
STK-REQ-013 SYS-REQ-019 derives STK environmental discharge limits → SYS environmental permitting
STK-REQ-003 SYS-REQ-018 derives STK safety case requirement → SYS DBA and basic safety levels
STK-REQ-010 SYS-REQ-017 derives STK 24-hour grid notification → SYS grid scheduling notification requirement
STK-REQ-016 SYS-REQ-005 derives EPZ size driven by maximum credible tritium release limited by containment requirement
STK-REQ-018 SYS-REQ-003 derives In-situ blanket measurement validates system-level TBR requirement
STK-REQ-014 SYS-REQ-014 derives Radioactive waste categorisation need drives reduced-activation materials requirement
STK-REQ-013 SYS-REQ-005 derives Environmental discharge limits derive tritium containment requirement
STK-REQ-012 SYS-REQ-012 derives Radiation zone access control derives system dose rate requirement
STK-REQ-010 SYS-REQ-010 derives Grid scheduling drives availability requirement
STK-REQ-003 SYS-REQ-011 derives Safety case drives seismic response requirement
STK-REQ-020 SYS-REQ-014 derives Material activation minimisation drives waste target
STK-REQ-019 SYS-REQ-014 derives Decommissioning timeline drives material selection requirement
STK-REQ-017 SYS-REQ-013 derives Research data need drives diagnostic system specification
STK-REQ-015 SYS-REQ-012 derives Public dose limit drives shielding to reduce off-site contribution
STK-REQ-011 SYS-REQ-012 derives Worker dose limit drives neutron shielding requirement
STK-REQ-009 SYS-REQ-015 derives Grid connection need drives power quality requirements
STK-REQ-009 SYS-REQ-002 derives Net power output drives conversion efficiency
STK-REQ-009 SYS-REQ-001 derives Net power output drives plasma performance requirement
STK-REQ-008 SYS-REQ-005 derives Automatic tritium isolation drives containment architecture
STK-REQ-007 SYS-REQ-003 derives Fuel cycle closure drives breeding ratio requirement
STK-REQ-006 SYS-REQ-009 derives Maintenance campaign duration drives RH throughput
STK-REQ-005 SYS-REQ-009 derives Remote handling need drives system-level RH specification
STK-REQ-004 SYS-REQ-003 derives Tritium accountability drives breeding ratio measurement
STK-REQ-003 SYS-REQ-007 derives Safety case drives passive safety for loss of coolant
STK-REQ-003 SYS-REQ-006 derives Safety case drives quench protection requirements
STK-REQ-003 SYS-REQ-005 derives Safety case requirement drives tritium double containment
STK-REQ-003 SYS-REQ-004 derives Safety case requirement drives disruption mitigation as DBA response
STK-REQ-002 SYS-REQ-004 derives Operator emergency shutdown need drives disruption mitigation timing
STK-REQ-001 SYS-REQ-013 derives Operator display requirement drives diagnostic system specification