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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.
D. Ingman, E. Taviv
Nuclear Science and Engineering | Volume 92 | Number 4 | April 1986 | Pages 550-569
Technical Paper | doi.org/10.13182/NSE86-A18612
Articles are hosted by Taylor and Francis Online.
Mapping of source-hydrogenous medium systems within the framework of three-group diffusion theory is discussed. Each system is presented by the point of the map with coordinates: X ratio of first- and second-group diffusion lengths, and Г ratio of slowing down and thermal diffusion lengths. This mapping leads to the method of source-medium systems classification, which reduces the phase space of the problem. In accordance with this method, source-medium systems can be characterized by only two parameters, scale and shape. Thermal flux in the systems with the same shape parameter can be described with the same “generalized flux function (GFF).” The approach of GFFs is investigated for direct and inverse problems. The first one is presentation of thermal flux for certain source-medium systems with the help of these functions, and the second one is estimation of medium neutron transport parameters from the measured thermal flux through GFFs.