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Division Spotlight
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.
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.
Anton Lüthi, Rakesh Chawla, Gérald Rimpault
Nuclear Science and Engineering | Volume 138 | Number 3 | July 2001 | Pages 233-255
Technical Paper | doi.org/10.13182/NSE01-A2211
Articles are hosted by Taylor and Francis Online.
A new calculational scheme has been developed for the accurate assessment of gamma heating in fast reactors, its special feature being the determination of the gamma source distribution that is formulated in a near-to-exact manner. The improved methodology, which has been implemented into the ERANOS (European Reactor Analysis Optimized System) code package, is currently validated for Pu-burning configurations, for which gamma-heating target accuracies are particularly high. This has been accomplished through comparisons with new integral measurements conducted at the MASURCA facility, as well as with reevaluated earlier experiments. In the new measurements, absolute gamma-heating rates were determined in PuO2/UO2-fueled cores surrounded by a steel/sodium reflector, mainly using TLD-700 thermoluminescent dosimeters. Thereby, a considerable effort was undertaken to minimize systematic errors. The calculation/experiment values determined from the analysis of the critical experiments are 0.90 for the PuO2/UO2 core region, 0.84 for the steel/sodium reflector, and 0.89 for an internal steel/sodium diluent zone. The most plausible causes for the observed discrepancies have been identified to be data related, i.e., too low fission gamma energies and too low capture cross sections for the structural elements. The transferability of the current validation findings to a modified Superphénix configuration, in which the radial fertile blanket is replaced by a steel/sodium reflector, and to the 1500 MW(electric) Pu-burning CAPRA 4/94 reference design has been demonstrated.
