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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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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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.
M. Makai, E. Temesvári
Nuclear Science and Engineering | Volume 112 | Number 1 | September 1992 | Pages 66-77
Technical Paper | doi.org/10.13182/NSE92-A23952
Articles are hosted by Taylor and Francis Online.
Surveillance of a nuclear reactor core involves determination of the power or temperature distribution of the assemblies. Derived from other assemblies’ measured temperatures, the temperature of a nonmeasured assembly is calculated for every assembly with the help of the principal components method (PCM). The basis of this method is presented, and the measured values are interpolated for various geometrical coverings of the WWER-440 core. A number of procedures have been elaborated and investigated, the most successful of which are introduced. Each method offers self-consistent means for determining the numerical errors of the interpolated values. The procedure based on the PCM can be utilized for any reactor type and is fairly accurate.