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Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Candidates for leadership provide statements: ANS Board of Directors
With the annual ANS election right around the corner, American Nuclear Society members will be going to the polls to vote for a vice president/president-elect, treasurer, and members-at-large for the Board of Directors. In January, Nuclear News published statements from candidates for vice president/president-elect and treasurer. This month, we are featuring statements from each nominee for the Board of Directors.
M. S. Kazimi, J. C. Chen
Nuclear Technology | Volume 38 | Number 3 | May 1978 | Pages 339-366
Critical Review | doi.org/10.13182/NT78-A32033
Articles are hosted by Taylor and Francis Online.
The analyses performed to evaluate the capacity to contain the core materials after a hypothetical core meltdown accident are generally grouped under the area of post-accident heat removal (PAHR). Substantial advancement in the state-of-the-art of the PAHR area has occurred within the last few years. The key issues of PAHR, as applied to safety analyses of liquid-metal breeder reactors, are summarized in this Review. The Review includes heat source strength for post-accident conditions, in-vessel core debris retention, ex-vessel core debris retention, and the effects of alternative fuel materials.