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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.
Yutaka Furuta, Yoshihiko Kanemori
Nuclear Science and Engineering | Volume 30 | Number 2 | November 1967 | Pages 261-267
Technical Paper | doi.org/10.13182/NSE67-A17336
Articles are hosted by Taylor and Francis Online.
Gamma-ray dose rates from a 60Co cylindrical source were obtained experimentally in the radial direction at the half-height of the source. The concept of the dose buildup factor was introduced for a volume source. The dose buildup factor for a cylindrical source, which is represented as a function of the distance between source and detection point, has a value of about five at the point nearest to the source surface. The factor then decreases rapidly, passes through a minimum value, and approaches a constant value. These features were analyzed experimentally with a line and a disk source. An empirical formula for the dose buildup factor is proposed which agrees with the experimental values to within about ± 15%.
