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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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Latest News
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.
Keith Humenik, Kenny C. Gross
Nuclear Science and Engineering | Volume 105 | Number 4 | August 1990 | Pages 383-390
Technical Paper | doi.org/10.13182/NSE90-A21472
Articles are hosted by Taylor and Francis Online.
The properties of sequential probability ratio tests (SPRTs) and the application of these tests to nuclear power reactor operation are examined. Recently, SPRTs have been applied to delayed neutron (DN) signal data analysis using actual reactor data from the Experimental Breeder Reactor II (EBR-II), which is operated by Argonne National Laboratory. The implementation of this research as part of an expert system is described. Mathematical properties of the SPRT are investigated, and theoretical results are validated with tests that use DN signal data taken from the EBR-II in Idaho. Variations of the basic SPRT and applications to general signal validation are also explored.
