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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
Meeting 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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Latest News
DOE extends Centrus’s HALEU production contract by one year
Centrus Energy has announced that it has secured a contract extension from the Department of Energy to continue—for one year—its ongoing high-assay low-enriched uranium (HALEU) production at the American Centrifuge Plant in Piketon, Ohio, at an annual rate of 900 kilograms of HALEU UF6. According to Centrus, the extension is valued at about $110 million through June 30, 2026.
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.