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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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October 2024
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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.
A. W. Hare, S. Aifant, F. A. Rough, D. I. Slnizer
Nuclear Science and Engineering | Volume 10 | Number 1 | May 1961 | Pages 24-30
Technical Paper | doi.org/10.13182/NSE61-A25925
Articles are hosted by Taylor and Francis Online.
The results of the postirradiation examinations on UC compounds having nominal compositions of 4.6, 4.8, and 5.0 w/o C continue to be encouraging after irradiation to approximate burnups of from 1000 to 15,000 MWD/Ton of U. Density changes were small varying from a minimum of 0.7% to a maximum of about 2.5%. Cracking has occurred in all specimens, however, it can probably be largely attributed to thermal stresses. Depletion of carbon is occurring in the specimens having the nominal 5 w/o C composition. Metallographic examination shows that these specimens appear to revert to the 4.8 w/o C stoichiometric composition. The fission gas retention properties of this material appear quite good. In all cases, the amount of fission gas released is comparable to the calculated amount released by recoil.
