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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.
A. Razani, S. Yee, M. Nagel
Nuclear Technology | Volume 33 | Number 3 | May 1977 | Pages 264-274
Technical Paper | Fuel | doi.org/10.13182/NT77-A31788
Articles are hosted by Taylor and Francis Online.
For the design of control elements for a gas-cooled fast breeder reactor, accurate heat generation rates in the element must be known. The nuclear heating rates in all sections of the control element and the contribution of all radiation sources to the distribution of nuclear heating in the element are evaluated. The emphasis is placed on the direct neutron heating of the B4C control rod and on gamma-ray transport and energy deposition in the stainless-steel cladding and guide tube. The calculations include the helium and tritium production within the B4C control rod.
