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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Albert Kreuser, Jörg Peschke
Nuclear Technology | Volume 136 | Number 3 | December 2001 | Pages 255-260
Technical Paper | Reactor Safety | doi.org/10.13182/NT01-A3243
Articles are hosted by Taylor and Francis Online.
The quantification of common-cause failures (CCFs) is often connected with uncertainties in how to interpret observed CCF events and with how far they are applicable to the specific group of components in question. A method has been developed that allows consideration of these kinds of uncertainties on the basis of a modification of the Binomial-Failure-Rate model. The quantification of interpretation uncertainties by means of interpretation alternatives is discussed as well as their effects on the estimation of the coupling parameter of the underlying CCF model. The estimation of the coupling parameter under consideration of the aforementioned uncertainties is performed by a Bayesian approach. To facilitate the specification of interpretation uncertainties, a default proposal of the interpretation vector is automatically generated on the basis of component fault states gained by expert judgment. Modification of the default vector is possible depending on engineering judgment of technical or operational differences between the observed and the target group of components.