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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
Standards Program
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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Article considers incorporation of AI into nuclear power plant operations
The potential application of artificial intelligence to the operation of nuclear power plants is explored in an article published in late December in the Washington Examiner. The article, written by energy and environment reporter Callie Patteson, presents the views of a number of experts, including Yavuz Arik, a strategic energy consultant.
André Puill, Jean Bergeron
Nuclear Technology | Volume 119 | Number 2 | August 1997 | Pages 123-140
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT97-A35381
Articles are hosted by Taylor and Francis Online.
An objective is to enhance the use of plutonium in conventional or slightly modified pressurized water reactors, while minimizing minor actinide production. Having entirely mixed-oxide-fueled reactors reduces the number of reactors that are affected on plutonium recycling and avoids the need for fuel zoning. However, the overall consumption is <30%, and the mass of minor actinides produced is considerable, representing up to 25 % of the plutonium used. The Advanced Plutonium Fuel Assembly concept, based on a uranium-free plutonium fuel, which achieves high burnups and an increased moderation ratio, enables 60% of the second-generation plutonium to be consumed, while the minor actinides produced only represent 8% of this figure. The heterogeneous design of the fuel assembly, which includes natural uranium or low-enriched uranium fuel rods, guarantees values that suit the physical parameters of the core. The concept was analyzed from a thermo-hydraulic aspect in both rated and accident situations. Technological feasibility is yet to be demonstrated. This study is part of a medium-term strategy for the back end of the fuel cycle.