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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.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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New laws offer nuclear industry incentives for existing power plant uprates
This year, the U.S. nuclear industry received a much-needed economic boost that could help preserve operating nuclear power plants and incentivize upgrades that extend their lifespan and power output.
Signed into law in 2022, the Inflation Reduction Act offers production tax credits (PTCs) for existing nuclear power plants and either PTCs or investment tax credits (ITCs) for new carbon-free generation. These credits could make power uprates—increasing the maximum power level at which a commercial plant may operate—a much more appealing option for utilities.
Hangbok Choi, Won Il Ko, Myung Seung Yang
Nuclear Science and Engineering | Volume 135 | Number 2 | June 2000 | Pages 150-164
Technical Paper | doi.org/10.13182/NSE00-A2131
Articles are hosted by Taylor and Francis Online.
A method to reduce the fuel composition heterogeneity effect on the core performance parameters has been studied for DUPIC fuel, which is made from spent pressurized water reactor (PWR) fuel by a dry refabrication process. This study focuses on the reactivity control method, which uses slightly enriched, depleted, or natural uranium to minimize the additional cost on the manufacturing of DUPIC fuel, when adjusting the excess reactivity of the spent PWR fuel. To reduce the variation of isotopic composition of the DUPIC fuel, interassembly mixing operations were assumed to be carried out three times. Three options have been considered: reactivity control by slightly enriched and depleted uranium, reactivity control by natural uranium for high-reactivity spent PWR fuels, and reactivity control by natural uranium for intermediate-reactivity spent PWR fuels. The results of this study have shown that the reactivity of DUPIC fuel can be tightly controlled with the minimum amount of fresh uranium feed. For reactivity control by slightly enriched and depleted uranium, all spent PWR fuel can be utilized as DUPIC fuel, and the fraction of fresh uranium feed is 3.4% on the average. For reactivity control by natural uranium, ~88% of spent PWR fuel can be utilized as DUPIC fuel when intermediate-reactivity spent PWR fuels are used, and the amount of natural uranium feed needed to control the DUPIC fuel reactivity is negligible.