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Division Spotlight
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.
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.
C. E. Johnson, S. W. Tam, P. E. Blackburn, D. C. Fee
Nuclear Technology | Volume 57 | Number 1 | April 1982 | Pages 104-113
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A16190
Articles are hosted by Taylor and Francis Online.
Venting and pressure equalization of gas-cooled fast breeder reactor (GCFR) fuel rods can be maintained only as long as axial gas transport paths are available and operating within the fuel pin. Analysis of the chemistry expected within an irradiated GCFR fuel pin shows that axial gas transport paths may become plugged due to the migration of fission product cesium and the formation of low density cesium-urania or cesium-fuel compounds. Cesium transport in the fuel and blanket is controlled by oxygen concentrations and by temperature distribution. Analysis of the shorter Experimental Breeder Reactor II in-reactor fuel pins suggests cesium will be retained in the much longer fast test reactor pins. This will lead to minimal plugging of the gas transport paths.
