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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
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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.
P. d'Oultremont, J. C. Young, J. M. Neill, C. A. Preskitt
Nuclear Science and Engineering | Volume 45 | Number 2 | August 1971 | Pages 141-155
Technical Paper | doi.org/10.13182/NSE71-A20881
Articles are hosted by Taylor and Francis Online.
A subcritical time-of-flight spectrum facility (STSF) has been used to study the neutron spectra and kinetics of two fast assemblies designated STSF-2 and STSF-2A. Neutron spectra have been measured by the time-of-flight method between 5 MeV and 500 eV in the core and the reflector of the STSF-2 which is essentially the same as the ZPR-3 Assembly 17. The STSF-2 core was loaded with plate type elements and the neutron spectrum was determined at the surface of a graphite plate, an enriched uranium plate, and a depleted uranium plate. Detailed transport calculations have been performed with ENDF/B version 1 cross sections and compared to the experimental data which had been reduced by an original method. Finally, kinetic measurements have been performed on assembly STSF-2A which confirm the validity of the time-dependent calculations involved in the time-of-flight data analysis.