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2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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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Modernizing I&C for operations and maintenance, one phase at a time
The two reactors at Dominion Energy’s Surry plant are among the oldest in the U.S. nuclear fleet. Yet when the plant celebrated its 50th anniversary in 2023, staff could raise a toast to the future. Surry was one of the first plants to file a subsequent license renewal (SLR) application, and in May 2021, it became official: the plant was licensed to operate for a full 80 years, extending its reactors’ lifespans into 2052 and 2053.
Michael L. Corradini, James P. Blanchard, Carl J. Martin
Nuclear Science and Engineering | Volume 168 | Number 3 | July 2011 | Pages 185-196
Technical Paper | doi.org/10.13182/NSE10-24
Articles are hosted by Taylor and Francis Online.
The occurrence of a steam explosion for advanced light water reactors (LWRs), whether within or below the reactor pressure vessel in the cavity, is analyzed to determine the possible hazard to structures as a result of dynamic explosion pressures. In current LWRs, in-vessel steam explosions have been determined not to pose a risk-significant threat, while ex-vessel explosions are considered in safety analyses. In advanced LWRs, such analyses are important to demonstrate that such structures will maintain their integrity so that core debris coolability is possible. This paper presents an approach to calculate the dynamic pressures from a steam explosion using the TEXAS-V model and evaluate its effects on surrounding structures using ANSYS. Scenarios for advanced LWRs are reviewed, and a severe accident scenario is used as an example to present our methodology. Such evaluation methods should be considered in future safety studies and be verified with direct comparison to data for energetic fuel-coolant interaction, such as those provided from past KROTOS tests or with current experiments in the international SERENA project.