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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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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.
K. Zwijsen, D. Dovizio, P. A. Breijder, F. Alcaro, , F. Roelofs (NRG)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 935-944
CIRCE is a test facility designed and realized by the Italian agency ENEA to support the heavy liquid metal technology for nuclear fission plants. Within the H2020 projects MYRTE and SESAME, various experiments will be performed in this facility, using two different heat exchangers, resembling nominal operation and accident scenarios of a Liquid Metal Fast Reactor (LMFR). Simultaneously, within these projects different thermal-hydraulics models of CIRCE are created to gain experience in the modelling of such a facility and to help future development of LMFRs. At NRG, both an STH and CFD model of CIRCE in two different configurations, are created. These two models are to be coupled eventually. The present paper describes these two models. Results obtained with these models are, where possible, compared with experimental results, both for steady-state and transient conditions. For the steady-state, generally good agreement is found. The transient simulation performed recovers some of the main features of the experiment, however excessive cooling is found. The cause is currently under investigation, which is complicated due to the lack of experimental data.