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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.
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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
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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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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.
M. E. Dunn
Nuclear Science and Engineering | Volume 142 | Number 1 | September 2002 | Pages 48-56
Technical Note | doi.org/10.13182/NSE02-A2286
Articles are hosted by Taylor and Francis Online.
The Reich-Moore (RM) formulation is used extensively in many isotope/nuclide evaluations to represent neutron cross-section data for the resolved-resonance region. The RM equations require the evaluation of complex matrices (i.e., matrices with complex quantities) that are a function of the resonance energy and corresponding resonance parameters. Although the RM equations are documented in the open literature, computational pitfalls may be encountered with the implementation of the RM equations in a cross-section processing code. Based on experience, numerical instabilities in the form of nonphysical oscillations can occur in the calculated absorption, capture, or elastic scattering cross sections. To illustrate possible numerical instabilities, the conventional RM equations are presented, and the conditions that lead to numerical problems in the cross-section calculations are identified and demonstrated for 28Si and 60Ni. In an effort to circumvent the computational problems, detailed or revised RM expressions have been developed to efficiently and accurately calculate cross sections for neutron-induced reactions in the resolved-resonance region. The revised equations can be used to avoid numerical problems associated with the implementation of the RM formulation in a cross-section processing code. The revised Reich-Moore equations are also used to demonstrate the improved cross-section results (i.e., without numerical instabilities) for 28Si and 60Ni.