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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Donald L. Smith, J. W. Meadows, Frank F. Porta
Nuclear Science and Engineering | Volume 78 | Number 4 | August 1981 | Pages 420-424
Technical Note | doi.org/10.13182/NSE81-A21378
Articles are hosted by Taylor and Francis Online.
An experimental facility has been developed for short-half-life neutron activation studies. Sample material is transported between the irradiation position and the counting position by a constant-velocity cog belt. This facility has been used to measure the 53Cr(n,p)52V cross section relative to the 52Cr(n,p)52V cross section below 9.4 MeV, using elemental chromium metal as a sample material. The measured ratios and previously reported cross-section information for the 52Cr(n,p)52V have been used to derive values for the 53Cr(n,p)53V cross section. The 235U thermal-neutron fission spectrum average has been calculated from the differential results, and comparison is made with reported integral data.
