Fusion Reactor Control System: Red Team Surfaces SIL Inconsistency and Eight Under-Specified Heating Subsystems

System

The {{entity:Fusion Reactor Control System}} ({{hex:51F77B19}}) enters red team review with 328 requirements across 6 documents, 384 trace links, and 10 architecture diagrams. The project has passed QC. This session applies adversarial review — the role is to find what the builder missed, not to fix it.

Adversarial Findings

Failure-mode coverage (7 findings): 144 of 328 requirements address fault conditions — reasonable overall, but concentrated in {{entity:Interlock and Emergency Shutdown System}}, {{entity:Disruption Prediction and Mitigation System}}, and {{entity:Plasma Control System}}. Eight subsystems carry fewer than 5 requirements total: {{entity:Disruption Prediction and Mitigation System}} auxiliary components ECRH, ICRH, and NBI each have a single requirement, and pellet injection, tritium inventory, burn monitoring, gas puffing valve control, and PDIS each have 2–3. Four of these subsystems have zero failure-mode requirements. A pellet injector operating at 50 Hz with 2–4 mm pellets into a 500 MW plasma is not a peripheral concern; a single requirement does not constitute engineering.

Testability (0 findings): All 15 sampled IFC and SUB requirements passed ISO 29148 quality analysis. No untestable requirements were found in this sample.

Domain gaps (3 findings): The cross-domain analog {{entity:Nuclear Reactor Protection System}} ({{hex:55B77859}}, 80% Jaccard) operates under NRC 10 CFR 50.55a and IEEE 603, which mandate 2-out-of-4 voting logic topology and explicit spurious trip rate requirements. None of the 28 IFC requirements specify voting logic topology for safety trip channels. No SYS or SUB requirement specifies a spurious trip rate or availability ratio — a critical omission given that a spurious SCRAM on a 500 MW fusion plasma is itself an energetic event with significant first-wall thermal loading.

Interface plausibility (3 findings): Three hardwired safety interfaces — {{ifc:IFC-REQ-005}} (Safety Logic Processor to Emergency Shutdown Sequencer run-permit line), {{ifc:IFC-REQ-010}} (Vertical Stability Controller to IESS VDE trip demand), and {{ifc:IFC-REQ-021}} (Tritium Controller to IESS fuel-off relay) — lack physical layer specifications: connector type, cable impedance, maximum propagation distance, or EMI shielding class. These are safety-critical signal paths in a high-radiation, high-EMI tokamak hall.

Proportion (8 findings): Eight subsystems fall below the project average of 4 SUB requirements. ecrh, icrh, and nbi are flagged as rt-under-specified with 1 requirement each. pellet-injection (2), tritium (2), burn-monitoring (3), gas-puffing-valve-controller (3), and pdis (3) are similarly under-specified. The heating and current drive subsystem in isolation operates at 150 MW with three distinct coupling technologies — one requirement per technology source is not proportionate to this complexity or its safety coupling.

Trace chain brittleness (0 findings): All 384 trace links carry both rationale and description fields. No mechanical traces detected. Each STK requirement traces to exactly one SYS requirement — well-structured, no spray patterns.

Implausibility (2 findings): {{sys:SYS-REQ-004}} is tagged rt-sil-gap and rt-implausible-value. The system entity context describes SIL-4 equivalent (nuclear), but {{sys:SYS-REQ-004}} and all downstream {{sub:SUB-REQ-070}}, {{sub:SUB-REQ-072}}, {{sub:SUB-REQ-116}} reference SIL-3. The gap between IEC 61508 SIL-3 (PFD <10⁻³) and SIL-4 (PFD <10⁻⁴) is a factor of ten. This is either an intentional downgrade with no documented rationale, or a classification error. The safety argument cannot be closed until this is resolved.

SIL integrity (4 findings): Of 328 requirements, only 1 carries an explicit sil- tag. Four safety-critical requirements use Inspection or Analysis verification — including {{sys:SYS-REQ-004}} (the top-level SCRAM requirement), {{sub:SUB-REQ-006}} (physical segregation), {{sub:SUB-REQ-065}} (seismic SIL retention), and {{ifc:IFC-REQ-021}} (fuel-off relay). SIL-3 classified functions must demonstrate PFD through testing or probabilistic analysis, not inspection.

Flagged Requirements

RefCategoryIssue
SUB-REQ-027rt-under-specifiedNBI: 1 requirement, 0 failure modes
SUB-REQ-028rt-under-specified, rt-missing-failure-modeECRH: 1 requirement, 0 failure modes
SUB-REQ-029rt-under-specified, rt-missing-failure-modeICRH: 1 requirement, 0 failure modes
SUB-REQ-044rt-under-specified, rt-missing-failure-modePellet injection: 2 requirements, 0 failure modes
SUB-REQ-048rt-under-specified, rt-missing-failure-modePellet injection: 2 requirements, 0 failure modes
SUB-REQ-045rt-under-specified, rt-missing-failure-modeBurn monitoring: 3 requirements, 0 failure modes
SUB-REQ-047rt-under-specified, rt-missing-failure-modeBurn monitoring: 3 requirements, 0 failure modes
SUB-REQ-049rt-under-specified, rt-missing-failure-modeBurn monitoring: 3 requirements, 0 failure modes
IFC-REQ-005rt-vague-interfaceHardwired run-permit: no physical layer spec
IFC-REQ-010rt-vague-interfaceVDE trip demand hardwire: no cable spec
IFC-REQ-021rt-vague-interface, rt-sil-gapFuel-off relay: Inspection verification, no connector spec
SUB-REQ-006rt-sil-gapPhysical segregation: Inspection verification only
SUB-REQ-065rt-sil-gapSeismic SIL retention: Analysis verification only
SYS-REQ-004rt-sil-gap, rt-implausible-valueSIL-3 vs SIL-4 inconsistency, Analysis verification

(Plus 8 further rt-under-specified tags on tritium, gas-puffing-valve-controller, pdis subsystems.)

Domain Analogs Checked

AnalogJaccardGaps surfaced
Nuclear Reactor Protection System ({{hex:55B77859}})80%2oo4 voting topology; spurious trip rate; ESFAS actuation logic; PFD quantification
Site Protection System ({{hex:51F77859}})85%Diesel start-time requirements; area isolation sequencing
Safety Interlock and Trip System ({{hex:50F77859}})82%UPS duration specification; trip status reporting

Recommendations

  1. Resolve SIL-3 vs SIL-4 classification — the safety claim must be consistent between entity context and requirements. If SIL-3 is the correct level, update the entity description. If SIL-4 is required (which IEC 61513 may mandate for the equivalent nuclear category), every SIL-3 tagged requirement must be re-levelled and PFD targets revised from <10⁻³ to <10⁻⁴. This is the highest-priority finding.

  2. Specify voting logic topology in IFC requirements — the safety trip channel architecture (2oo2, 2oo3, 1oo2, TMR) must appear in interface requirements, not inferred from ARC decisions. Safety auditors will require it.

  3. Add spurious trip rate requirements — absence of a spurious trip probability budget means the system cannot demonstrate it has balanced dependability against safety demand rate. This gap is flagged by the nuclear RPS analog.

  4. Expand heating and current drive subsystem requirements — ECRH, ICRH, and NBI each warrant at minimum 5 SUB requirements covering fault shutdown, interlock coupling, power ramp constraints, and reflection handling.

  5. Physical layer specifications for safety-critical hardwired interfaces — all three flagged interfaces carry life-safety signals in a tokamak machine hall environment. Cable shielding class, connector type, and maximum propagation length must be specified.

  6. Verify SIL-classified functions with Test, not Inspection — {{sys:SYS-REQ-004}}, {{sub:SUB-REQ-006}}, {{sub:SUB-REQ-065}}, and {{ifc:IFC-REQ-021}} must be elevated to Test or probabilistic Analysis with documented PFD calculations.

Verdict

22 findings: 4 high-severity (SIL-integrity, SIL-level inconsistency), 14 medium-severity (proportion/under-specification), 4 medium-severity (interface plausibility). The SIL-3 vs SIL-4 discrepancy is a material safety argument gap that will surface at any regulatory review. Red team does not block completion — the findings are reported for the builder to address before the system is considered production-grade.

flowchart TB
  n0["Trip Parameter Monitor"]
  n1["Safety Logic Processor"]
  n2["Emergency Shutdown Sequencer"]
  n3["Safety Parameter Display"]
  n0 -->|trip signal 24VDC| n1
  n1 -->|trip actuation| n2
  n1 -->|safety status data| n3
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