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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.
Hideo Matsuzuru, Noboru Moriyama
Nuclear Science and Engineering | Volume 80 | Number 1 | January 1982 | Pages 14-25
Technical Paper | doi.org/10.13182/NSE82-A21400
Articles are hosted by Taylor and Francis Online.
The leaching behavior of a cement composite incorporating evaporator concentrates produced at a pressurized water reactor nuclear power plant has been studied for safety assessment of the final disposal of waste solids. Leaching tests were carried out in accordance with the method recommended by the International Atomic Energy Agency. Amounts leached were measured as functions of the waste-cement weight ratio (Wa/C), temperature of leachant, and curing time of specimens. The solidification of wastes containing boric acid with cement-vermiculite mixture was much improved by the alkalinization of the waste up to pH 12. The fraction of 3H or 90Sr leached increases with increasing Wa/C and leachant temperature, and with decreasing curing time. The amount of either 137Cs, 60Co, or 144Ce leached does not depend much on Wa/C, but depends on the leachant temperature and curing time. The leaching fraction for these nuclides in de-ionized water as a leachant is higher than that in the synthetic seawater. The leachabilities of nuclides follow the order: 3H > 137Cs > 90Sr > 60Co > 144Ce. The relationship between the fraction leached and the ratio of surface area and volume of a specimen has been examined in order to estimate the amounts leached from specimens of various geometries. On the basis of the results obtained, estimations were made of the amounts leached from a 200-ℓ composite volume that is exposed to a water environment for extended periods.
