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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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.
B. F. Gore, B. R. Leonard, Jr.
Nuclear Science and Engineering | Volume 53 | Number 3 | March 1974 | Pages 319-323
Technical Note | doi.org/10.13182/NSE74-A23356
Articles are hosted by Taylor and Francis Online.
Calculations have been performed which indicate the possibility of reducing below ten years the effective half-life for transmutation of massive loadings of 137Cs placed in the blanket of a controlled thermonuclear reactor (CTR). The calculations assume the cylindrical “standard blanket” geometry and neutron source (which yields a vacuum wall loading of 10 MW/m2 of 14-MeV neutrons). Significant thermal flux enhancement is obtained by (n,2n) reactions in a beryllium moderator. Gas production and induced radioactivity problems in the beryllium moderator are not much worse than in a graphite moderator. For an 80% target-zone loading of 137Cs, a transmutation rate of 290 kg per year per meter of CTR length is obtained. At this loading, the transmutation rate in roughly 1% of the length of a CTR blanket would balance the production rate in a fission reactor of the same power. Constraint of the CTR source strength to yield a wall loading of 1 MW/m2 would increase the effective half-life for 137Cs to more than 20 years.