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Decommissioning & Environmental Sciences
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
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.
H. Kwast
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 234-240
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32322
Articles are hosted by Taylor and Francis Online.
Capsule irradiations have been performed on single fast reactor fuel pins in a sodium environment under simulated loss-of-coolant-flow conditions. The main objectives were to determine the thresholds, modes, and mechanisms of fuel pin failures. The parameters were canning temperature and internal pin pressure. The loss-of-coolant-flow condition was simulated by adjusting midwall canning temperatures of ∼850 and ∼1000°C. The results indicated that creep rupture is the predominant failure mechanism at canning temperatures of 1000°C and gas pressures of above 40 bars. The failure mechanism of fuel pins tested at ∼850°C and gas pressures lower than 60 bars is probably cladding strain due to differential expansion of fuel and canning.
