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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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Powering the future: How the DOE is fueling nuclear fuel cycle research and development
As global interest in nuclear energy surges, the United States must remain at the forefront of research and development to ensure national energy security, advance nuclear technologies, and promote international cooperation on safety and nonproliferation. A crucial step in achieving this is analyzing how funding and resources are allocated to better understand how to direct future research and development. The Department of Energy has spearheaded this effort by funding hundreds of research projects across the country through the Nuclear Energy University Program (NEUP). This initiative has empowered dozens of universities to collaborate toward a nuclear-friendly future.
George Apostolakis, Ali Mosleh
Nuclear Science and Engineering | Volume 70 | Number 2 | May 1979 | Pages 135-149
Technical Paper | doi.org/10.13182/NSE79-A19646
Articles are hosted by Taylor and Francis Online.
A model for the evaluation of probabilities of rare events by combining the available experience with expert opinion is developed, using the core melt frequency of nuclear power reactors as an example. A distribution for this frequency is assessed using the statistical evidence and including “near misses.” This distribution is subsequently modified, via Bayes' theorem, to include the estimate derived by the Reactor Safety Study, which is treated as an expert's opinion. A probabilistic model for the credibility of this opinion that includes the critics' point of view is presented. The resulting (posterior) distribution is the assessed distribution of the frequency of reactor core melts based on a body of knowledge that includes the available experience and the WASH-1400 estimate.