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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
Standards Program
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.
M. Sugimoto, P. T. Guenther, J. E. Lynn, A. B. Smith, J. F. Whalen
Nuclear Science and Engineering | Volume 103 | Number 1 | September 1989 | Pages 37-45
Technical Paper | doi.org/10.13182/NSE89-A23658
Articles are hosted by Taylor and Francis Online.
Neutron total cross sections of elemental beryllium are measured from 1 to 10 MeV with good precision. Differential neutron elastic scattering cross sections are measured from 4.5 to 10 MeV at intervals of ≈0.5 MeV and at ≈100 angular steps distributed between ≈18 and 160 deg at each incident energy. Concurrently, differential cross sections for the emission of a discrete inelastic neutron group corresponding to an excited level at (2.43 ± 0.06) MeV are determined over the same incident energy and angular range. Angle-integrated elastic scattering cross sections are deduced from the observed differential values to accuracies of ≈2.5%, and angle-integrated inelastic scattering cross sections to accuracies of ≈10%. The experimental results are compared with values given in ENDF/B-V, with attention to discrepancies and implications. Qualitative reaction mechanisms are suggested.