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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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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.”
Karl Schleisiek, Jürgen Aberle, Siegfried Jacobi, August Rahn, Lothar Schmidt, Gilbert Vanmassenhove, Alfons Verwimp
Nuclear Technology | Volume 99 | Number 3 | September 1992 | Pages 289-300
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34713
Articles are hosted by Taylor and Francis Online.
The aim of the MoI-7C in-pile local blockage experiments is to ascertain the consequences of local cooling disturbances in fuel subassemblies of liquid-metal fast breeder reactors. The experiments are carried out in the BR2 reactor at Mol/Belgium within the framework of a joint program of Kernforschungszentrum Karlsruhe and Studiecentrum voor Kernenergie/Centre d’Etude de VEnergie Nucleaire Mol. The last two experiments, Mol-7C/6 and 7, performed with the support of the Joint Research Centre Ispra in June 1988 and June 1989, respectively, are dealt with. The particular objective of these two tests is to investigate the consequences of local faults at high burnup and of blockages having contact with the subassembly wrapper tube. The test sections, the performance of the tests, and the results obtained are described. A preliminary interpretation is presented.
