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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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May 2025
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.
R. T. Santoro, R. G. Alsmiller, Jr., J. M. Barnes, T. A. Gabriel
Nuclear Science and Engineering | Volume 105 | Number 3 | July 1990 | Pages 278-289
Technical Paper | doi.org/10.13182/NSE90-A19192
Articles are hosted by Taylor and Francis Online.
The Monte Carlo codes MORSE and MCNP have been used to calculate the tritium production from ≈ 14-MeV neutron reactions in a Li2O assembly. Tritium production from neutron reactions with 6Li and 7Li nuclei were calculated along the central axis of a 0.60-m-diam × 0.60-m-long assembly and four additional assemblies where sheets of Type 304 stainless steel and polyethylene were placed in front of the Li2O to simulate first-wall and coolant materials. The calculated data are compared with measured data obtained at the Fusion Neutron Source at the Japan Atomic Energy Research Institute. The calculated data reproduce the measured data in shape, but differ from the measured data by 10 to 20% in the case of 6Li and as much as 30% at some spatial locations for the 7Li tritium production.
