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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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Latest News
Atomic Canyon partners with INL on AI benchmarks
As interest and investment grows around AI applications in nuclear power plants, there remains a gap in standardized benchmarks that can quantitatively compare and measure the quality and reliability of new products.
Nuclear-tailored AI developer Atomic Canyon is moving to fill that gap by entering into a new strategic partnership with Idaho National Laboratory to develop and release the “first comprehensive benchmark suite for evaluating retrieval-augmented generation (RAG) and large language models (LLMs) in nuclear applications.”
Shlomo Ron, Judah Tzoref
Nuclear Technology | Volume 96 | Number 1 | October 1991 | Pages 37-49
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT91-A35532
Articles are hosted by Taylor and Francis Online.
The potential release of fission products during a beyond-design accident in a medium-sized high-temperature gas reactor (the HTR-500) is investigated. The DSNP modular simulation code is used to simulate a depressurization accident as well as the failure of the forced circulation of the decay heat removal systems to actuate. For such an extreme accident, the calculated maximum localized fuel temperature reaches 3040° C 43 h after the beginning of the accident. During the heatup, 3.4% of the 137Cs inventory is found to be released from the fuel elements to the primary circuit, and 4.6 × 10−2% is estimated to be released into the environment. The carbon monoxide and helium releases from the graphite matrix prove to be an important factor in sweeping the fission products from the primary circuit. The comparative consequence analysis indicates a much lower risk than in the analogous light water reactor severe accident. A design-base depressurization accident is also investigated at the beginning of the study and involves the operation of one out of the two redundant decay heat removal systems.
