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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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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.
G. Winkler, V. Spiegel, C. M. Eisenhauer, D. L. Smith
Nuclear Science and Engineering | Volume 78 | Number 4 | August 1981 | Pages 415-419
Technical Note | doi.org/10.13182/NSE81-A21377
Articles are hosted by Taylor and Francis Online.
The average cross section for the reaction 63Cu(n, α)60Co has been measured absolutely in the 252Cf spontaneous fission neutron field by activation in compensated flux geometry with an accuracy of ∼2.4% (1α). A near-point source of 252Cf and a light mass source-detector assembly in a low-scattering environment was used. The resulting cross-section value was compared with calculated values obtained by convoluting the spectral distribution of 252Cf neutrons with existing energy-differential data for the reaction 63Cu(n, α)60Co. There is very good agreement (within 5%) between the experimental and the calculated average cross section if the results from a recent measurement of the 63Cu(n, α)60Co excitation function are used. Thus the reaction 63Cu(n, α)60Co, which is an important threshold reaction in reactor dosimetry, fulfills the conditions for a Category I neutron-dosimetry reaction for fission reactor applications.
