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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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.
Edgar Kiefhaber
Nuclear Science and Engineering | Volume 111 | Number 2 | June 1992 | Pages 197-204
Technical Note | doi.org/10.13182/NSE92-A23933
Articles are hosted by Taylor and Francis Online.
For high-accuracy criticality calculations, one should take into account the difference in the energy distributions between prompt and delayed fission neutrons. In steady-state reactor calculations, it is usually assumed that delayed and prompt neutrons are emitted with the same energy distribution. This approximation may lead to systematic deviations in keffof between −0.2 and +0.05%. While for typical cores of liquid-metal-cooled fast reactors and corresponding critical assemblies the effect is usually fairly small, it may become more important for low-enriched k∞ experiments and for highly enriched, high-leakage cores. For group cross-section adjustment procedures usually covering a wide range of critical assemblies with fairly different nuclear characteristics, a proper treatment of the energy distributions of delayed neutrons could be particularly important for excluding systematic differences as far as possible.