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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
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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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.
W. Baer
Nuclear Science and Engineering | Volume 10 | Number 1 | May 1961 | Pages 57-60
Technical Paper | doi.org/10.13182/NSE61-A25930
Articles are hosted by Taylor and Francis Online.
A measurement of the epithermal radiative capture in U238 has been carried out in a natural UO2-fueled blanket cluster of the nuclear mock-up of PWR Core 1. Analysis indicates that a substantial increase (∼20%) in epithermal captures in a natural uranium metal plate fuel cluster should occur in the fuel elements adjacent to a wide intercluster water channel. The experiment shows that the captures in a cylindrical UO2 fuel element at the edge of the bundle is only 7% greater than in a neighboring fuel element. However, the radial distribution of captures in the first fuel rod shows that the captures near the wide intercluster water channel are 65% greater than at an equivalent position on the side of the rod away from the water channel. Calculations of the relative epithermal U238 captures in the cluster have shown that diffusion theory predicts the spatial dependence of the captures in the interior of the cluster but fails near the edge of the bundle. Monte Carlo analysis confirms the observed increase in the captures in a fuel rod at the edge of the bundle, although the precision of the analysis does not make a quantitative comparison feasible.