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Division Spotlight
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.
Meeting Spotlight
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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August 2024
Latest News
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.
C. B. Bigham, S. A. Kushneriuk, P. R. Tunnicliffe
Nuclear Science and Engineering | Volume 16 | Number 3 | July 1963 | Pages 299-314
Technical Paper | doi.org/10.13182/NSE63-A26533
Articles are hosted by Taylor and Francis Online.
Fission cross section ratios of U233, U235, and Pu239 and capture rates in Mn55 and In115 have been measured in an NRX type uranium metal rod irradiated in a heavy water moderated reactor. The results have been compared to the values obtained using a model designed for NRX burnup calculations. Agreement was obtained using an “incurrent” spectrum composed of a Maxwellian thermal component and an epithermal component of the form obtained from neutron spectrometer measurements. Changes in spectrum caused by the light water coolant were also studied.