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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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Latest News
NRC v. Texas: Supreme Court weighs challenge to NRC authority in spent fuel storage case
The State of Texas has not one but two ongoing federal court challenges to the Nuclear Regulatory Commission that could, if successful, turn decades of NRC regulations, precedent, and case law on its head.
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.