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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
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
DOE extends Centrus’s HALEU production contract by one year
Centrus Energy has announced that it has secured a contract extension from the Department of Energy to continue—for one year—its ongoing high-assay low-enriched uranium (HALEU) production at the American Centrifuge Plant in Piketon, Ohio, at an annual rate of 900 kilograms of HALEU UF6. According to Centrus, the extension is valued at about $110 million through June 30, 2026.
Warren F. Witzig, Ross T. Thomas
Nuclear Science and Engineering | Volume 69 | Number 2 | February 1979 | Pages 251-263
Technical Paper | doi.org/10.13182/NSE79-A20615
Articles are hosted by Taylor and Francis Online.
Multidimensional linear regression analysis is employed as a modeling technique for the prediction of boiling water reactor (BWR) shutdown margin reactivity. A comparison is made between the best models developed using regression analysis and the General Electric (GE) three-dimensional BWR core simulator code. The GE code is based on one-group diffusion theory, and its accuracy is verified by comparison with experimental data. One use of this code is the calculation of shutdown margin throughout a fuel cycle, but it requires a large computing facility not located at a reactor site. The regression models give an approximation of a core's shutdown margin based on current core physics parameters. The method can be utilized at a BWR plant site to provide information demonstrating compliance with license and technical specification requirements. The results obtained by regression predictions for the two cores studied compare favorably with current industry methods. After establishing a regression model, predictions can be made at a reactor site using a pocket calculator.