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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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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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Keeping up with Kewaunee
In October 2012, Dominion Energy announced it was closing the Kewaunee nuclear power plant, a two-loop 574-MWe pressurized water reactor located about 27 miles southeast of Green Bay, Wis., on the western shore of Lake Michigan. At the time, Dominion said the plant was running well, but that low wholesale electricity prices in the region made it uneconomical to continue operation of the single-unit merchant power plant.
W. H. Martin, D. M. Clare
Nuclear Science and Engineering | Volume 18 | Number 4 | April 1964 | Pages 468-473
Technical Paper | doi.org/10.13182/NSE64-A18765
Articles are hosted by Taylor and Francis Online.
Fast-neutron dose measurement by the activation of nickel foils involves a correction for thermal-neutron burnup of Co58, the daughter product of the (n,p) reaction. Fast-neutron irradiation of nickel produces Co58 in its ground and excited isomeric states, and recently the isomer has been shown to have a high thermal-neutron-absorption cross section. This paper considers how the determination of fast-neutron dose by nickel activation should be corrected for thermal-neutron burn-up of both ground and isomeric states of Co58. Results, which have been fully corrected, are compared with results obtained at low reactor power where the thermal-neutron burn-up of Co58 and Co58m is negligible. All the data considered were obtained from foils irradiated in rigs in hollow fuel elements in reactors of the DIDO type. The data demonstrate that accurate fast-neutron dose measurements, using nickel activation, in high-flux facilities can only be made if the thermal-neutron cross sections of Co58 and Co58 m and the branching ratio of the Ni58 (n,p) reaction have previously been determined in the neutron spectrum being utilised.