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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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
Katy Huff reflects on her time in the Office of Nuclear Energy
After three years in the Department of Energy, including two as assistant secretary of the Office of Nuclear Energy, Katy Huff stepped down in May to return to the world of academia as a professor at the University of Illinois–Urbana-Champaign.
Among her many accomplishments while serving as NE-1, Huff pushed for energy security—both at home and abroad, in places like war-torn Ukraine—and for the development of additional advanced and traditional nuclear plants, the potential restart of shuttered nuclear facilities, and a better funding stream for college nuclear programs.
M. Drosg, R. Avalos Ortiz, P. W. Lisowski
Nuclear Science and Engineering | Volume 172 | Number 1 | September 2012 | Pages 87-101
Technical Paper | doi.org/10.13182/NSE11-66
Articles are hosted by Taylor and Francis Online.
Much of the absolute differential cross-section data for elastic scattering by 3He depends on an experiment at the Los Alamos National Laboratory (LANL), published in 1974. Since that time, computer techniques have been developed that can make more accurate corrections for, e.g., sample-size effects. Since complete documentation of the LANL experiment is available, modern analysis techniques were applied to improve these data, based on simulations using the Los Alamos Monte Carlo neutron transport code MCNPX. Of a total of 29 published differential cross-section distributions, 15 published in 1982 from another laboratory depend on the LANL data but were not corrected for sample-size effects and therefore provide only relative yield functions. The present study simulates these latter data using MCNPX to obtain self-attenuation correction factors for the scattered neutrons. An energy-dependent analysis shows that at neutron energies between 5 and 14 MeV, these latter corrected data are in good agreement with the other data, whereas above 22 MeV they are not. A complete energy-dependent analysis of all absolute differential cross sections between 5 and 23.7 MeV is presented.