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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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.
Min Lee, Jan Sea Wu
Nuclear Science and Engineering | Volume 111 | Number 1 | May 1992 | Pages 82-101
Technical Paper | doi.org/10.13182/NSE92-A23925
Articles are hosted by Taylor and Francis Online.
Releases of radionuclides and the production of aerosols during the molten core/concrete interaction (MCCI) phase of degraded core accidents in light water reactors are termed “ex-vessel releases.” The VANESA and METOXA codes were respectively developed by the U.S. Nuclear Regulatory Commission and the Industrial Degraded Core Rulemaking (IDCOR) program to quantify ex-vessel releases. Comparison of calculations by VANESA and METOXA (under identical initial and boundary conditions) show that except for niobium and strontium species, the predicted ex-vessel radionuclide release rates are within an order of magnitude of each other. In an actual application of these two codes to the source term quantification of severe accidents, the initial and boundary conditions for the calculations could be significantly different, as demonstrated in an analysis of an anticipated transient without scram accident sequence in a boiling water reactor. For the same amount of debris, the MCCI thermal-hydraulic results provided for METOXA from a DECOMP calculation tend to drive more radioactive material from the debris pool than those provided for VANESA from a CORCON/MOD2 calculation. The MAAP code, however, predicts that less mass is involved in the MCCI.