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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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
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.
M. Corradini, H.H. Reineke
Nuclear Science and Engineering | Volume 102 | Number 3 | July 1989 | Pages 260-282
Technical Paper | doi.org/10.13182/NSE102-260
Articles are hosted by Taylor and Francis Online.
The results from the BETA molten core/concrete interaction (MCCI) experiments conducted at Kernforschungszentrum Karlsruhe (KfK) and the associated analyses using computer models developed by KfK and by Sandia National Laboratories, i.e., WECHSL and CORCON, are described. Two important observations were made in the BETA steady-state tests: The first observation could be modeled by WECHSL and CORCON by modifications when interface heat transfer considered a “transition boiling” analogy model. The second observation was not modeled but is expected to be important during the high-temperature phase of the MCCI when fission product release is of concern. These results suggest that the BETA experiments provide necessary information to validate MCCI models for silicate (basaltic) concrete. For limestone (carbonatic) concrete, there are still open questions that further tests must address.