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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.
Ryuji Koga
Nuclear Science and Engineering | Volume 61 | Number 2 | October 1976 | Pages 239-249
Technical Paper | doi.org/10.13182/NSE76-A27357
Articles are hosted by Taylor and Francis Online.
A burnup control problem during a reactor core life is considered and solved by making use of a neutron-governing equation that is particularly devised to fit power reactors. Space-dependent parameters are expanded using Walsh functions, and the burnup process is described in terms of the expansion coefficients. By applying the Walsh-function expansion to a newly devised neutron-governing equation, CUMULUS, the criticality condition is established through a more simplified approach, and the system structure of a two-region reactor can be illustrated graphically. Using the above burnup model, an optimal control problem to maximize the average burnup at the end of a core life is considered, and numerical test problems are solved.