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Mathematics & Computation
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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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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2024: The Year in Nuclear—July through September
Another calendar year has passed. Before heading too far into 2025, let’s look back at what happened in 2024 in the nuclear community. In today's post, compiled from Nuclear News and Nuclear Newswire are what we feel are the top nuclear news stories from July through September 2024.
Stay tuned for the top stories from the rest of the past year.
Edward A. Boucheron, John E. Kelly
Nuclear Technology | Volume 87 | Number 4 | December 1989 | Pages 1050-1057
Late Paper | TMI-2: Decontamination and Waste Management / Nuclear Safety | doi.org/10.13182/NT89-A27696
Articles are hosted by Taylor and Francis Online.
The MELCOR computer code has been used to analyze the first 174 min of the Three Mile Island Unit 2 (TMI-2) accident. MELCOR is being developed at Sandia National Laboratories for the U.S Nuclear Regulatory Commission for the purpose of analyzing severe accidents in nuclear power plants. Comparison of the code predictions to the available data shows that MELCOR is capable of modeling the key events of the TMI-2 accident, and reasonable agreement with the available data is obtained. In particular, the core degradation and hydrogen generation models agree with best-estimate information available for this phase of the accident. While the code uses simplified modeling, all important characteristics of the reactor system and the accident phenomena could be modeled. This exercise demonstrates that MELCOR is applicable to severe accident analysis.