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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.”
Hans-Werner Wiese
Nuclear Technology | Volume 102 | Number 1 | April 1993 | Pages 68-80
Technical Paper | Mixed-Oxide Fuel / Nuclear Fuel Cycle | doi.org/10.13182/NT93-A34803
Articles are hosted by Taylor and Francis Online.
Based on the use of the Joint Evaluated File (JEF-1) with the KARBUS burnup code system and subsequent KORIGEN code calculations, the characteristics of spent pressurized water reactor mixed-oxide (MOX) fuels are analyzed. Actinide masses, decay heat, radioactivities, and radiation are discussed for burnups of 40 to 55 GWd/tonne HM for MOX fuels based on natural uranium and on uranium tailings. Multiple plutonium recycling is considered at a burnup of 50 GWd/tonne HM. The results are compared with earlier data at a burnup of 33 GWd/tonne HM. The high-exposure MOX fuels are found to contain large amounts of the heat-releasing and radiating nuclides, 238Pu and 244Cm. The 238Pu in the plutonium, which is to be used for the fabrication of fuel elements from recycled MOX, requires special shielding or a change from glove box techniques to an automated treatment.
