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Nuclear Nonproliferation Policy
The mission of the Nuclear Nonproliferation Policy Division (NNPD) is to promote the peaceful use of nuclear technology while simultaneously preventing the diversion and misuse of nuclear material and technology through appropriate safeguards and security, and promotion of nuclear nonproliferation policies. To achieve this mission, the objectives of the NNPD are to: Promote policy that discourages the proliferation of nuclear technology and material to inappropriate entities. Provide information to ANS members, the technical community at large, opinion leaders, and decision makers to improve their understanding of nuclear nonproliferation issues. Become a recognized technical resource on nuclear nonproliferation, safeguards, and security issues. Serve as the integration and coordination body for nuclear nonproliferation activities for the ANS. Work cooperatively with other ANS divisions to achieve these objective nonproliferation policies.
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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.
B. K. Malaviya, N. N. Kaushal, M. Becker, E. T. Burns, A. Ginsberg, E. R. Gaerttner
Nuclear Science and Engineering | Volume 47 | Number 3 | March 1972 | Pages 329-348
Technical Paper | doi.org/10.13182/NSE72-A22419
Articles are hosted by Taylor and Francis Online.
As part of a comprehensive program devoted to the integral checks of differential microscopic cross-section data pertinent to the LMFBR program, the experimental and analytical investigations of fast neutron transport in bulk assemblies of iron are described. Time-of-flight measured fast-neutron angular flux spectra at different positions in a simple, clean, homogeneous assembly are analyzed using ENDF/B data as input, MC2 code system, and SN transport calculations. In addition, continuous slowing down theory has been developed to complement precise calculations by indicating direct relationships between cross-section uncertainties and spectra; this approach permits integrating other non-ENDF/B data in the analysis. The well-defined integral experiment permits clear-cut interpretation leading to definitive conclusions with respect to input data and also to checks of standard analytical codes. The Karlsruhe (KEDAK) data set and the ENDF/B-I and ENDF/B-II files for iron have been assessed. On the basis of cross-section uncertainties in iron and of their influence on spectra, it is possible to recommend not only preferred data, but also a redirection in emphasis in differential measurements and evaluation. For fast reactor applications, ENDF/B-I set is prefer able, subject to certain limitations.