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The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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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
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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.
Henri Fenech and Henri M. Guéron
Nuclear Science and Engineering | Volume 31 | Number 3 | March 1968 | Pages 505-512
Technical Paper | doi.org/10.13182/NSE68-A17594
Articles are hosted by Taylor and Francis Online.
The principal methods of core design uncertainly analysis are critically reviewed. The overconservatism of the Deterministic Method, which aims at ensuring that the design limits cannot be exceeded in the most loaded channel (or at the most loaded spot), leads to a probabilistic approach (the Statistical Method) in which the probability of such an event is evaluated. Recent work in this direction is discussed. It is emphasized, however, that a probabilistic reliability evaluation must cover the whole core, and not only its most heavily loaded element. The Synthesis Method presented here fulfills this requirement without demanding the use of computers. The Synthesis Method also allows the use of a realistic space-dependent reliability criterion. The various methods under review are compared in their application to a fast gas-cooled reactor core. The power levels corresponding to a given reliability are calculated and the Synthesis Method is seen to be more conservative than the classical Statistical Method and less conservative than the Deterministic Method.