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Mathematics & Computation
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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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.
H. D. Knox, R. M. White, R. O. Lane
Nuclear Science and Engineering | Volume 69 | Number 2 | February 1979 | Pages 223-230
Technical Paper | doi.org/10.13182/NSE79-A20612
Articles are hosted by Taylor and Francis Online.
Differential cross sections for neutrons scattered elastically from 6Li and 7Li have been measured at 14 incident neutron energies between 4 and 7.5 MeV. For 7Li, neutrons inelastically scattered from the 0.478 MeV-level were not resolved from the elastic group and have been included with the elastic group in calculating the cross sections. The present 6Li data are in good agreement with the ENDF/B-IV evaluation, while the present 7Li(n,n0 + n1) data are generally larger than the corresponding ENDF/B-IV evaluation particularly at forward angles.
