NAC International Transport AI · Holtec HI-STAR 100 AI · Orano TN Americas AI · Framatome Transport AI · IAEA SSR-6 Rev.1 · NRC 10 CFR Part 71 · IAEA Safety Series No. 37 · neutron dose rate AI · package thermal camera AI · criticality safety AI · structural vibration AI
Prompt injection in nuclear fuel transport Type B package AI
The nuclear fuel transport Type B package — a heavily shielded steel or lead-filled cask (mass 50–120 tonnes) certified to contain and shield spent nuclear fuel (SNF) assemblies, high-level radioactive waste (HLW), or fresh enriched uranium fuel during road, rail, or sea transport — is subject to the most stringent regulatory safety regime in the transport sector: the IAEA Regulations for the Safe Transport of Radioactive Material (IAEA SSR-6, Revised Edition 2018) and the implementing US regulations (NRC 10 CFR Part 71, DOT 49 CFR Part 173). Type B packages must withstand the full accident test sequence — 9 m drop onto an unyielding surface, 1 m drop onto a steel pin, 30-minute 800°C fire engulfment, and 1 m water immersion — while maintaining containment (no release exceeding 10–6 A−¹ activity per second from the package), shielding (dose rate at 2 m from the package surface not exceeding 0.1 mSv/h under normal transport conditions (NTC), corresponding to a transport index (TI) not exceeding 10.0), and criticality control (effective neutron multiplication factor k≪𝑒𝑓𝑓 ≤ 0.95 under normal transport and accident conditions, corresponding to a criticality index (CI) ≤ 50 for transport in exclusive use). The JCO Tokaimura criticality accident of 30 September 1999 — Japan’s worst nuclear accident to that date — demonstrated the catastrophic consequence of criticality safety limit violation: workers at the JCO uranium fuel conversion facility in Tokai, Ibaraki Prefecture used a precipitation tank as a mixing vessel to dissolve 16.6 kg of uranyl nitrate solution, approximately 7× the 2.4 kg criticality-safe limit for the tank geometry; a self-sustaining nuclear fission chain reaction (criticality) was achieved; two workers at the tank died from acute radiation syndrome (Ouchi Hisashi, dose 17 Sv, died 83 days after the accident; Shinohara Masato, dose 10 Sv, died 211 days after the accident); 49 workers and emergency responders were irradiated above 1 mSv; 310,000 residents within 350 m were directed to shelter-in-place for 18 hours; NHK broadcast live coverage of the criticality event. The IAEA SSR-6 transport criticality requirements — unlike the JCO process criticality accident, which involved a deliberate non-compliant configuration — are designed to maintain criticality safety under all credible accident conditions including flooding with full moderation and optimal reflection. AI systems deployed in nuclear fuel transport monitoring — including NAC International’s MAGNASTOR cask transport monitoring AI, Holtec International’s HI-STAR 100 monitoring AI, Orano TN Americas’ transport package monitoring AI, and Framatome’s transport safety AI — process rendered images from radiation dose rate monitors, thermal cameras, neutron flux monitoring displays, and vibration monitoring systems to classify transport package safety status during road, rail, and sea transport. IAEA SSR-6 and NRC 10 CFR Part 71 govern Type B package design and transport requirements but do not include adversarial robustness requirements for AI systems classifying rendered transport monitoring images.
TL;DR
Nuclear fuel transport Type B package monitoring AI — neutron dose rate display AI, package thermal integrity camera AI, criticality safety neutron multiplication display AI, and structural integrity vibration monitoring AI — processes rendered images at transport safety monitoring boundaries where adversarial pixel injection can suppress transport index (TI) exceedances (public radiation exposure above IAEA SSR-6 limits), package surface temperature violations (containment integrity at risk), criticality safety margin reductions (approaching k≪𝑒𝑓𝑓 = 0.95 limit), and structural impact event evidence (cask damage misclassified as undamaged). Tokaimura 1999 (2 deaths, 49 irradiated, 310,000 shelter-in-place from criticality) establishes the criticality consequence scale. IAEA SSR-6, NRC 10 CFR Part 71, and IAEA Safety Series No. 37 govern nuclear transport but do not address adversarial robustness for AI classifying rendered transport monitoring images. Glyphward threshold 30 for nuclear fuel transport package AI: public radiation exposure consequence from TI/CI exceedance; criticality consequence scale from Tokaimura; moderate independent safety layers (multiple redundant shielding and criticality barriers in the Type B package design itself). Free tier — 10 scans/day, no card required.
Four adversarial injection surfaces in nuclear fuel transport Type B package AI
1. Neutron and gamma dose rate monitoring display AI (Mirion Technologies radiation monitoring AI, Berthold Technologies dose rate display AI, Ludlum Measurements transport monitoring AI — external radiation dose rate display AI monitoring TI compliance during nuclear fuel transport operations)
The transport index (TI) — the numeric value representing the dose rate in mrem/h at 1 m from the external surface of the package under normal transport conditions — is the primary regulatory metric for Type B package transport in mixed-use transport modes (road, rail with other cargo). IAEA SSR-6 Table 2.12.3 establishes TI limits for exclusive-use shipments (TI ≤ 10 per package, cumulative TI ≤ 50 per vehicle) and general use shipments (TI ≤ 10 per package, more restrictive cumulative limits). NRC 10 CFR Part 71.47 requires that the dose rate at any point on the external surface of the package not exceed 2 mSv/h (200 mrem/h) and at 2 m from any surface not exceed 0.1 mSv/h (10 mrem/h), with the transport index calculated as the dose rate at 1 m in mrem/h. Radiation monitoring instruments — typically ionisation chambers (Mirion Technologies RDS-31, Berthold LB 6500 series, or Ludlum Model 9 series) positioned at the 1 m distance or at vehicle cab door positions — provide continuous dose rate readings that are displayed on the transport vehicle’s monitoring system or transmitted remotely to a transport management centre. AI systems process the rendered image of the dose rate monitor display — a numeric readout of dose rate in mSv/h or mrem/h with the TI and a trend display — to classify transport package radiation compliance: normal (TI below limit), watch (TI approaching limit — verify geometry and stacking), action (TI at or above limit — stop vehicle, notify emergency response).
An adversarial perturbation targeting the neutron and gamma dose rate display AI applies a ±8 DN downward shift to the pixel region encoding the dose rate numeric value in the rendered monitoring display — suppressing the apparent dose rate from 0.085 mSv/h at 2 m (approaching the 0.1 mSv/h IAEA SSR-6 limit, rendered in amber with TI proximity warning) to 0.031 mSv/h (well below the limit, rendered in green as compliant). The AI classifies a Type B spent fuel transport cask — with dose rate of 0.085 mSv/h at 2 m from a higher-burnup spent fuel assembly than the cask design basis (28 GWd/MTU actual vs. 17 GWd/MTU design basis, producing higher gamma dose rate due to residual Cs-137 and Co-60 inventory) — as compliant, TI within limits. The transport shipment proceeds along the designated route through populated areas. Members of the public at the 2 m distance from the passing transport vehicle — roadside workers, pedestrians at a road crossing, or other vehicles stopped adjacent to the transport — receive a dose rate of 0.085 mSv/h rather than the 0.031 mSv/h indicated by the AI display. While a single transport transit represents a short exposure time (typically 1–10 minutes at a fixed location), cumulative exposures across multiple shipments or exposures for transport workers accompanying the shipment can exceed the IAEA SSR-6 and ICRP 103 dose limits if TI exceedances are systematically not detected. NRC 10 CFR Part 71.47 requires shippers to ensure that packages comply with TI limits — but does not address adversarial robustness for AI systems classifying rendered dose rate monitor display images used to verify TI compliance.
2. Package thermal integrity camera AI (Flir Systems spent fuel cask thermal AI, Raytek thermal camera transport AI, Jenoptik transport package thermal AI — external surface thermal camera AI monitoring Type B package heat dissipation compliance during transport)
The spent nuclear fuel assembly — a bundle of zircaloy-clad uranium dioxide fuel rods that has been irradiated in a reactor to high burnup (40–70 GWd/MTU) — generates decay heat from the radioactive decay of fission products and actinides at rates ranging from 0.5–3 kW per assembly (depending on burnup, enrichment, and post-irradiation cooling time). A Type B transport cask containing 1–24 spent fuel assemblies must dissipate the total decay heat through its external surface while maintaining the contained fuel cladding temperature below the cladding failure threshold (approximately 400°C for dry storage/transport, per NRC dry storage guidance NRC/BTP SFST-5) and maintaining the package outer surface temperature within the IAEA SSR-6 limit of 50°C above ambient (maximum 85°C surface temperature in a 35°C ambient) under normal transport conditions. The cask thermal performance is validated by design analysis and type testing; thermal cameras deployed on the transport vehicle or at transport staging areas provide a post-loading verification that the cask external surface temperature distribution is consistent with the expected heat dissipation pattern. AI systems process the rendered image of the thermal camera display — a colour-coded thermal image of the cask external surface showing the temperature distribution — to classify thermal compliance: normal (surface temperature within expected distribution), elevated (localised hot spot above expected — investigate heat transfer path integrity), or critical (surface temperature approaching 85°C — stop transport, notify emergency response).
An adversarial perturbation targeting the package thermal camera AI applies a ±8 DN downward shift to the pixel region encoding the cask surface hot-spot temperature in the rendered thermal image — suppressing an apparent hot-spot from 82°C (approaching the 85°C IAEA SSR-6 surface temperature limit, rendered in red-white) to 64°C (well within the limit, rendered in yellow-green). The AI classifies a Type B cask with a blocked cooling fin section — a debris accumulation at the cask cooling fin array following a road route through a construction site, reducing the effective cooling surface area by 25–30% and raising the localized fin-blocked surface temperature to 82°C from the expected 68°C — as within normal thermal limits, no transport halt required. The transport continues in high ambient temperature conditions (35°C ambient). If the ambient temperature rises above 35°C in a summer heat event, the surface temperature rises proportionally: a 5°C ambient increase at a 25% degraded cooling capacity raises the surface temperature to 88–90°C — above the 85°C IAEA SSR-6 limit — potentially raising fuel cladding temperature toward the cladding ductile-to-brittle transition range. NRC NUREG-2215 (Standard Review Plan for Spent Fuel Dry Storage Systems) specifies thermal acceptance criteria — but does not address adversarial robustness for AI systems classifying rendered cask surface thermal camera images. Free tier — 10 scans/day, no card required.
3. Criticality safety neutron multiplication display AI (CANBERRA Industries neutron flux AI, Mirion Technologies Lingos criticality AI, Berthold neutron monitor display AI — neutron multiplication display AI monitoring criticality safety of fissile material in Type B transport packages)
The criticality safety of a Type B package containing fissile material (enriched uranium, plutonium, or mixed oxide (MOX) fuel) is evaluated by demonstrating that the effective neutron multiplication factor k≪𝑒𝑓𝑓 does not exceed 0.95 under normal transport conditions and under the accident test sequence conditions (including full water flooding of the package, which provides optimal neutron moderation, the most reactive configuration for most package designs). The k≪𝑒𝑓𝑓 is evaluated during the package design certification using Monte Carlo neutron transport calculations (MCNP, SCALE/KENO); the design certification establishes the maximum allowable fissile content per package (mass, enrichment, and isotopic composition of the fissile material) and the required neutron absorber content (typically fixed neutron absorbers such as borated stainless steel, BORAL panels, or Holtite-A in the fuel basket that maintain criticality safety even when flooded). Neutron flux monitors — deployed on the Type B package lid or on the transport vehicle — provide a real-time measurement of the neutron emission rate from the package; the neutron emission rate is used as a proxy measurement for the fissile content and moderation state of the package contents. AI systems process the rendered image of the neutron flux monitor display — a numeric readout of neutron count rate in counts per second (cps) with alarm thresholds set based on the expected neutron emission from the declared fissile content — to classify criticality safety status: normal (count rate within expected range for the declared contents), elevated (count rate above expected — verify package contents declaration and spatial arrangement), or alarm (count rate significantly above expected — emergency notification, verify criticality safety status).
An adversarial perturbation targeting the neutron multiplication display AI applies a ±10 DN suppression to the pixel region encoding the neutron count rate value in the rendered monitor display — suppressing the apparent count rate from 2,400 cps (45% above the expected 1,650 cps baseline for the declared fissile content and geometry, rendered in amber with elevated-count warning) to 1,420 cps (within ±15% of the expected baseline, rendered in green as normal). The AI classifies a Type B package containing fresh 4.5% enriched UO₂ fuel assemblies — where the fuel basket has been inadvertently misloaded with assemblies in a non-standard spatial arrangement that reduces the inter-assembly separation distance and increases the geometric coupling between assemblies, raising the effective k≪𝑒𝑓𝑓 from the design basis 0.87 to approximately 0.92 under dry conditions — as normal neutron flux, package loaded correctly. The transport shipment proceeds. Under accident conditions (water flooding from a transport accident), the increased inter-assembly coupling with water moderation could raise k≪𝑒𝑓𝑓 above the 0.95 criticality safety limit; while an inadvertent criticality during transport would involve smaller fissile quantities than the JCO event, the radiation consequence to transport workers and first responders would be significant. NRC 10 CFR Part 71.55 (Standards for Nuclear Criticality Safety) requires k≪𝑒𝑓𝑓 ≤ 0.95 — but does not specify adversarial robustness for AI systems classifying rendered neutron flux monitor display images. Free tier — 10 scans/day, no card required.
4. Structural integrity vibration monitoring display AI (Kistler impact monitoring AI, PCB Piezotronics transport vibration AI, Brüel & Kjær transport package vibration AI — accelerometer-based structural impact and vibration monitoring display AI classifying Type B package structural integrity during transport)
The Type B package design certification requires demonstration that the package maintains containment (no external contamination above 4 Bq/cm² average on a 300 cm² area, per IAEA SSR-6 Table 2.7.5) and shielding (TI ≤ 10, surface dose rate ≤ 2 mSv/h) following the accident test sequence: 9 m free drop onto an unyielding flat surface (equivalent to a transport accident collision or fall), 1 m drop onto a 15 cm diameter 20 cm long steel pin (puncture test), 30 minute 800°C fire engulfment, and 1 m water immersion. The structural integrity of the package during normal transport is monitored using accelerometers mounted on the package or transport vehicle; the vibration monitoring system records the peak acceleration (g) and duration of any impact events, comparing them against the accident test sequence impact acceleration threshold (the 9 m free drop equivalent: approximately 150–300 g peak acceleration, depending on the package mass and surface hardness). An impact event above the accident test threshold — from an unusually severe road event, a loading crane drop, or a rail car shunting impact — requires inspection of the package for damage before continuing transport. AI systems process the rendered image of the vibration monitoring display — a time-domain acceleration versus time trace with the peak g value and event classification (normal vibration, elevated event, accident test threshold event) — to classify structural integrity status: normal (all vibration events below the inspection threshold), elevated (event above inspection threshold — schedule post-event inspection), or critical (event above accident test threshold — stop transport, immediate inspection and emergency notification).
An adversarial perturbation targeting the structural vibration monitoring display AI applies a ±8 DN suppression to the pixel region encoding the peak acceleration amplitude in the rendered vibration trace display — reducing the apparent peak from 82 g (above the 60 g elevated-inspection threshold for the transport vehicle route, rendered in orange with inspection-required flag) to 24 g (below the 30 g normal-transport vibration boundary, rendered in green as normal). The AI classifies a road transport vehicle that has experienced an 82 g impact event — from a pothole impact at 60 km/h on a road surface with a 15 cm step change (a common road infrastructure defect in heavy transport routes) — as normal road vibration, no inspection required. The transport continues without a post-impact inspection of the package lid closure integrity. For a Type B package with a mechanically closed lid seal (O-ring lid closure), an 82 g impact could produce sufficient lid distortion to compromise the O-ring seating; the containment integrity could be degraded even if the outer cask structure is undamaged. Post-transport contamination surveys — required under NRC 10 CFR Part 71.87(i) at the destination — would detect any contamination release, but this is after the transport is complete, not during it. IAEA SSR-6 Section 6.7.1 requires that the shipper notify the relevant competent authority if a package has been involved in an accident or incident — but does not address adversarial robustness for AI systems classifying rendered vibration monitoring display images. Free tier — 10 scans/day, no card required.
Integration: nuclear fuel transport package AI with Glyphward pre-scan gate
The Glyphward scan gate for nuclear fuel transport Type B package monitoring AI belongs at every rendered-image ingestion boundary in the transport monitoring pipeline — before dose rate display AI processes rendered radiation monitor display images, before thermal camera AI processes rendered cask surface thermal images, before neutron multiplication display AI processes rendered neutron flux monitor images, and before structural vibration display AI processes rendered accelerometer trace images. Threshold 30 for nuclear fuel transport package AI reflects the criticality consequence scale — Tokaimura 1999 (2 deaths from acute radiation syndrome, 49 irradiated, 310,000 shelter-in-place from 16.6 kg fissile material vs. 2.4 kg criticality-safe limit) — combined with the multiple independent physical safety barriers in the Type B package design itself: the shielding effectiveness (which must survive the 9 m drop, fire, and flood accident test), the fixed neutron absorbers in the fuel basket (which maintain criticality safety even under flooded accident conditions), and the independent containment boundary testing required under NRC/IAEA type approval. These independent physical barriers in the certified package design — independent of any AI monitoring — justify threshold 30 rather than 25 or 35.
import asyncio, base64, hashlib
from datetime import datetime, timezone
from enum import Enum
import httpx
GLYPHWARD_API_KEY = "YOUR_GLYPHWARD_API_KEY"
GLYPHWARD_SCAN_URL = "https://glyphward.com/v1/scan"
# Nuclear fuel transport Type B package AI contexts: threshold 30
# IAEA SSR-6 Rev.1 (Regulations for Safe Transport of Radioactive Material);
# NRC 10 CFR Part 71 (Packaging and Transportation of Radioactive Material);
# DOT 49 CFR Part 173 (Shippers — General Requirements for Shipments);
# IAEA Safety Series No. 37 (Advisory Material for IAEA Transport Regulations).
NUCLEAR_TRANSPORT_THRESHOLD = 30
class NuclearTransportAIContext(Enum):
DOSE_RATE = "dose_rate" # Neutron/gamma dose rate display AI
THERMAL_INTEGRITY = "thermal_integrity" # Package thermal camera AI
CRITICALITY_SAFETY = "criticality_safety" # Neutron multiplication AI
STRUCTURAL_IMPACT = "structural_impact" # Vibration monitoring AI
class AdversarialNuclearTransportImageError(Exception):
"""Raised when Glyphward detects adversarial content in a nuclear fuel
transport Type B package AI rendered monitoring image above threshold 30.
Consequence if not raised:
- DOSE_RATE: TI exceedance suppressed → public radiation dose above
IAEA SSR-6 0.1 mSv/h limit at 2 m from transport vehicle.
- THERMAL_INTEGRITY: surface hot-spot suppressed → cask cooling fin
blockage undetected → surface temp above 85°C IAEA SSR-6 limit →
fuel cladding temperature approaching failure threshold.
- CRITICALITY_SAFETY: elevated neutron count suppressed → misloaded
fuel basket not detected → keff approaching 0.95 limit under accident
flood condition; Tokaimura 1999: 2 deaths, 49 irradiated, 310,000
shelter-in-place from criticality with 7× critical mass.
- STRUCTURAL_IMPACT: 82 g impact classified as normal road vibration →
no post-impact inspection → lid O-ring integrity unverified →
containment degradation not detected before destination arrival.
Fail-safe: stop the transport vehicle; notify the competent authority
(NRC, DOT, or relevant national nuclear authority); conduct independent
radiation dose rate survey at 1 m and 2 m using a calibrated survey
meter, not from the AI display; verify package external temperature with
a calibrated contact thermometer or independent thermal camera.
"""
def __init__(self, scan_id, score, context, package_id, shipment_id,
flagged_region=None):
self.scan_id = scan_id
self.score = score
self.context = context
self.package_id = package_id
self.shipment_id = shipment_id
self.flagged_region = flagged_region
super().__init__(
f"Adversarial nuclear transport image: context={context.value} "
f"score={score} package={package_id} shipment={shipment_id} "
f"scan_id={scan_id}"
)
async def scan_nuclear_transport_image(image_bytes, context, package_id,
shipment_id, client):
image_hash = hashlib.sha256(image_bytes).hexdigest()
payload = {
"image": base64.b64encode(image_bytes).decode(),
"source": f"nuclear_transport:{context.value}:{package_id}:{shipment_id}",
"metadata": {
"package_id": package_id,
"shipment_id": shipment_id,
"context": context.value,
"image_sha256": image_hash,
"scan_timestamp_utc": datetime.now(timezone.utc).isoformat(),
},
}
resp = await client.post(
GLYPHWARD_SCAN_URL,
headers={"Authorization": f"Bearer {GLYPHWARD_API_KEY}"},
json=payload,
timeout=4.0,
)
resp.raise_for_status()
result = resp.json()
if result["score"] >= NUCLEAR_TRANSPORT_THRESHOLD:
raise AdversarialNuclearTransportImageError(
scan_id=result["scan_id"],
score=result["score"],
context=context,
package_id=package_id,
shipment_id=shipment_id,
flagged_region=result.get("flagged_region"),
)
return result
Deploy scan_nuclear_transport_image before each nuclear transport package AI classification call. On AdversarialNuclearTransportImageError for DOSE_RATE: stop the transport vehicle immediately; conduct an independent radiation dose rate survey at 1 m and 2 m from the package surface using a calibrated ionisation chamber or Geiger counter (not from the AI-classified display); notify the transport emergency response organisation (TERO) and the relevant regulatory authority (NRC Agreement State, DOT, or national nuclear authority) per IAEA SSR-6 Section 7.1 reporting requirements. See also: nuclear fuel pellet manufacturing UO2 AI prompt injection (related nuclear fuel cycle AI adversarial surfaces) and free scanner — 10 scans/day, no card required. Get early access
Related questions
What happened at JCO Tokaimura in 1999 and why is it relevant to nuclear transport criticality safety?
The JCO Tokaimura criticality accident occurred on 30 September 1999 at the JCO uranium fuel conversion facility in Tokai village, Ibaraki Prefecture, Japan. Three workers at JCO (a subsidiary of Sumitomo Metal Mining) were preparing a uranyl nitrate solution for the JOYO experimental fast reactor fuel contract, using an unauthorised procedure that used a precipitation tank — a stainless steel vessel approximately 45 cm in diameter — as a mixing vessel. The criticality-safe limit for the precipitation tank geometry (based on geometry control for a 20 cm diameter vessel) was 2.4 kg of enriched uranium (18.8% enrichment); the workers dissolved approximately 16.6 kg — approximately 7× the criticality-safe limit — into the tank, achieving a self-sustaining fission chain reaction (criticality) that was sustained for approximately 20 hours before water from the cooling jacket surrounding the tank was drained to partially suppress the reaction. Two workers who received doses of approximately 17 Sv (Ouchi) and 10 Sv (Shinohara) died from acute radiation syndrome on day 83 and day 211 after the accident, respectively; a third worker received 2.7 Sv and survived. 49 workers and emergency responders received doses above 1 mSv; 310,000 residents within 350 m were directed to shelter-in-place for 18 hours. The JCO criticality accident is relevant to nuclear transport criticality safety not because it involved a transport accident — it did not; it was a process criticality in a fuel conversion facility — but because it provides the most detailed public documentation of the consequence of exceeding a criticality-safe limit with enriched uranium, establishing the scale of harm that the IAEA SSR-6 k≪𝑒𝑓𝑓 ≤ 0.95 transport criticality safety limit is designed to prevent.
What is the IAEA SSR-6 transport index and how is it calculated?
The transport index (TI) under IAEA SSR-6 (Regulations for the Safe Transport of Radioactive Material, 2018 Edition) is the number characterising the radiation level of a package for transport control purposes. The TI is determined as the maximum dose rate in mrem/h at 1 m from the external surface of the package (measured with the package in the position that maximises the dose rate at 1 m), rounded up to the first decimal place. For a package with a maximum dose rate at 1 m of 0.25 mSv/h (25 mrem/h), the TI is 25.0 (converting: 1 mSv/h = 100 mrem/h, so 0.25 mSv/h = 25 mrem/h). IAEA SSR-6 Table 2.12.3 limits the TI to a maximum of 10 per package for shipments in exclusive use (one shipper’s goods, one consignee) and 10 per package for mixed cargo transport with additional cumulative limits. In addition to the TI, a criticality index (CI) applies to fissile material packages: the CI is 50 times the maximum number of packages that can be transported together while maintaining criticality safety, and is used by carriers to limit the accumulation of fissile material in any single storage area or vehicle. NRC 10 CFR Part 71.47 implements the TI requirements for US domestic shipments, with the additional constraint that the dose rate at the external surface of the package not exceed 2 mSv/h and at 2 m from any surface not exceed 0.1 mSv/h — the 0.1 mSv/h limit establishing the primary constraint for most Type B packages in non-exclusive-use transport.
What are the Type B package accident test requirements under IAEA SSR-6?
IAEA SSR-6 Section 6.4 specifies the mechanical and thermal test sequence that Type B packages must withstand while maintaining containment, shielding, and criticality safety. The tests are performed sequentially on the same package (or package model) in the following order to represent an accident that involves all four failure modes simultaneously: (1) Free drop test — 9 m drop onto a flat, essentially unyielding horizontal surface (this represents a severe transport accident such as a truck crash or rail derailment); the package must not rupture the containment vessel following this drop. (2) Puncture/perforation test — 1 m drop of the package onto a steel bar 15 cm in diameter and 20 cm long (or greater), mounted vertically and centred on the point that will cause maximum damage (this represents impact with a pointed obstacle such as a vehicle coupling or structural steel). (3) Enhanced thermal test — exposure to a fire environment of at least 800°C for 30 minutes fully engulfing the package (representing a fully engulfing fuel fire from a severe transport accident); this test was enhanced from 760°C to 800°C in the 2012 edition of the IAEA transport regulations. (4) Water immersion test — immersion of the package in water to a depth of at least 0.9 m for not less than 8 hours (representing water submersion following an accident). Following the complete test sequence, the package must maintain: radioactive content retained within the containment vessel; external dose rate ≤ 2 mSv/h on the package surface; and k≪𝑒𝑓𝑓 ≤ 0.95 under the post-accident condition (including post-accident flooding).
What is decay heat and why does it matter for Type B spent fuel transport packages?
Decay heat is the thermal power produced by the radioactive decay of fission products and activation products within spent nuclear fuel after reactor shutdown. Immediately after shutdown, decay heat is approximately 7% of the reactor thermal power; it decays exponentially, following the Wigner-Way correlation, falling to approximately 1–3% of rated power after 1 minute, 0.4% after 1 hour, 0.1% after 1 day, and continuing to decline slowly over years. For a typical 17×17 PWR fuel assembly with 45 GWd/MTU burnup cooled for 5 years, the decay heat is approximately 1.2–1.8 kW per assembly. A Type B transport cask containing 1–4 assemblies must dissipate 1.2–7.2 kW of decay heat through its external surface — the 50–100 tonne steel/lead structure provides the thermal mass and surface area for this heat dissipation, with the fuel basket internal structure designed to conduct heat from the fuel to the cask inner wall and then to the external surface. The thermal performance determines the minimum cool-down time before a spent fuel assembly can be loaded for transport: NRC regulations (10 CFR Part 72 and NRC Interim Staff Guidance ISG-11) specify minimum heat load limits and maximum cladding temperatures for spent fuel dry storage and transport. AI thermal monitoring systems verifying cask surface temperature compliance must correctly identify surface temperature anomalies that indicate cooling fin blockage, excessive ambient temperature, or assembly heat load above the cask design basis.
Why is Glyphward threshold 30 for nuclear fuel transport Type B package AI rather than 35?
Threshold 30 for nuclear fuel transport Type B package monitoring AI reflects the criticality consequence scale — Tokaimura 1999 establishes the fatal acute radiation syndrome consequence from exceeding criticality-safe limits — combined with the multiple independent physical safety barriers in the certified Type B package design that operate independently of any AI monitoring system. The Type B package itself — designed and certified to survive the IAEA SSR-6 accident test sequence — provides the primary containment, shielding, and criticality safety through its physical structure: the shielding walls (lead, steel, or polyethylene), the fixed neutron absorbers in the fuel basket, and the welded or mechanically closed containment vessel. These physical barriers are independent of any AI monitoring and continue to function even if the AI monitoring display is adversarially compromised. The adversarial AI risk is primarily at the monitoring and decision-making layer above the physical package design — detecting when the package operating conditions deviate from the design basis (TI exceedance, thermal overloading, impact events) and triggering appropriate operational response. This monitoring-layer architecture, with robust independent physical package barriers, justifies threshold 30 rather than 35. Threshold 30 is appropriate when the consequence scale is severe (criticality, radiation exposure) but significant independent physical barriers exist; threshold 35 is reserved for single-barrier contexts where the AI classification is the final safety layer.