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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.
Yigal S. Gur, Yair Bartal, Shimon Yiftah
Nuclear Science and Engineering | Volume 89 | Number 3 | March 1985 | Pages 217-232
Technical Paper | doi.org/10.13182/NSE85-A17543
Articles are hosted by Taylor and Francis Online.
Two-dimensional diffusion calculations, as commonly used, are unreliable for excess reactivity computations of small nuclear systems with significant leakage in the untreated dimension. Observing that the errors are mainly systematic, similarity between nuclear systems is defined and a theory concerning effective buckling is developed that eliminates systematic errors. Excess core reactivities of the materials-test-reactor-type swimming-pool research reactor IRR-1 are then computed with an accuracy better than ±0.5% with 99% confidence, and, in fact, the differences between the computed and measured values are <0.15% for the cases computed.