ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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.
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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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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.
J. P. Lestone, A. Gavron
Nuclear Science and Engineering | Volume 116 | Number 3 | March 1994 | Pages 213-217
Technical Paper | doi.org/10.13182/NSE94-A19814
Articles are hosted by Taylor and Francis Online.
A statistical model is used with parameters obtained by fitting 232U(n,f) through 236U(n,f) and 238U(n,f) cross-section data to determine the 237U(n,f) fission cross section in the neutron energy range of 0.5 to 20 MeV. Below an incoming neutron energy of 0.5 MeV, the cross section is extrapolated using the neutron energy dependence of the 235U(n,f) reaction. The calculated values to experimental 237U(n,f) cross-section data are compared, and some adjustments are made to the calculated values to obtain a better fit to the existing data.
