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Division Spotlight
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.
Meeting Spotlight
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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August 2024
Latest News
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.
W. N. McElroy, S. Berg, T. B. Crockett, R. J. Tuttle
Nuclear Science and Engineering | Volume 36 | Number 1 | April 1969 | Pages 15-27
Technical Paper | doi.org/10.13182/NSE69-A18853
Articles are hosted by Taylor and Francis Online.
A multiple foil activation iterative method has been used to experimentally determine neutron flux spectra in various types of neutron environments. The method involves irradiation of a set of different foil detectors, measurement of resultant activities, and adjustment of a spectrum selected as an initial approximation to obtain a good-fit solution for a set of simultaneous activation integral equations. A computer code, SAND-II, is used to obtain this solution. Spectra from thermal and fast reactors and from beam sources have been measured. In each experiment, a set of more than ten foil detectors, encompassing low- and high-energy neutron-induced reactions, was irradiated and used as input to SAND-II. Solutions obtained are compared with diffusion, transport, or Monte Carlo calculations or with spectrometer measurements. It is concluded that the multiple foil activation iterative method is an important adjunct to calculational and neutron spectrometer techniques used to determine neutron flux spectra.