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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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.
J. D. Garrison, B. W. Roos
Nuclear Science and Engineering | Volume 12 | Number 1 | January 1962 | Pages 115-134
Technical Paper | doi.org/10.13182/NSE62-A25379
Articles are hosted by Taylor and Francis Online.
Experimental measurements of fission product capture cross sections and statistical estimates of capture cross sections for energies at which no measurements have been made have yielded a set of group cross sections for primary and secondary fission products covering the complete range of energies of interest for reactor calculations. Capture cross sections and fission product yield measurements have been obtained from a comprehensive search covering published and some unpublished measurements available prior to May 1961. Unmeasured capture cross sections in the resonance region have been statistically estimated using average neutron strength functions, level spacings, and radiation widths. The general techniques of obtaining reliable nuclear parameters and estimates of cross sections are discussed in detail. The importance of capture in short-lived fission products is considered. The group cross sections obtained in this work have been combined and presented in a form useful for calculating fission product poisoning in reactors containing U233, U235, and/or Pu239. Results are analyzed and compared with previously published fission product studies.