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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
2023 ANS Annual Meeting
June 11–14, 2023
Indianapolis, IN|Marriott Indianapolis Downtown
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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Latest News
The Civil Nuclear Credit Program: An overview
Officially established on November 15, 2021, with the signing of the $1.2 trillion Infrastructure Investment and Jobs Act—aka the Bipartisan Infrastructure Law, or BIL—the Department of Energy’s Civil Nuclear Credit Program was designed to give owners/operators of commercial U.S. reactors the opportunity to apply for certification and competitively bid on credits to help support the continued operation of economically troubled units. Finally, the federal government, and not just certain farsighted state governments, would recognize nuclear energy for its important grid reliability and decarbonization attributes.
Yongdeok Lee, Jung Won Lee, Joo-Hwan Park
Nuclear Technology | Volume 179 | Number 1 | July 2012 | Pages 97-105
Technical Paper | Special Issue on Safeguards / Fuel Cycle and Management | doi.org/10.13182/NT12-A14070
Articles are hosted by Taylor and Francis Online.
The evaluation of proliferation resistance on the DUPIC fuel cycle was performed using the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) user manual. The user manual was finally published from INPRO as a tool for proliferation resistance evaluation. Five user requirements were well organized under one basic principle, and each evaluation parameter for each user requirement has criteria for qualitative and quantitative evaluation for an innovative nuclear system. The DUPIC fuel cycle is to fabricate CANDU fuel from spent pressurized water reactor fuel by use of a dry thermal process without separating the stable fission products. The DUPIC process and fabricated fuel have very intense radiation background and a low amount of fissile plutonium and uranium. The DUPIC fuel cycle has a number of intrinsic features that enhance proliferation resistance. The number of assemblies in the DUPIC process to get 1 significant quantity is very large ([approximately]48 assemblies). The assessment results using the user manual show that the DUPIC fuel cycle is very strong against nuclear proliferation by the material property itself and the facility condition. Additionally, several suggestions and conditions were made to increase the proliferation resistance for innovative future nuclear energy system.
