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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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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.
Richard E. Kaiser, William R. Kimel
Nuclear Science and Engineering | Volume 20 | Number 4 | December 1964 | Pages 468-475
Technical Paper | doi.org/10.13182/NSE64-A20989
Articles are hosted by Taylor and Francis Online.
Several methods are available for the determination of thermal diffusion length. In general, those based on one-group diffusion theory are subject to the assumption of a particular source boundary condition. Errors introduced by the assumption of such boundary conditions usually result in incorrect prediction of the relative harmonic content of the thermal flux at different elevations in the pile. The effect of these errors on diffusion-length determination is to cause inconsistency in the results as additional data points taken close to the source are included. A method is presented whereby the constants Amn in the one-group thermal-flux equation are determined experimentally and used in the determination of diffusion length. This method is then compared with other methods using one-group and age-diffusion theory with respect to the consistency of results obtained.