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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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June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
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.
Dan Gabriel Cepraga, Gilio Cambi, Manuela Frisoni
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 1088-1092
Neutronics Experiments and Analyses | doi.org/10.13182/FST96-A11963095
Articles are hosted by Taylor and Francis Online.
This paper summarises and discusses the results of the material damage assessment for the in-vessel components of the International Tokamak Experimental Reactor (ITER), with reference to the baseline design defined in the Interim Design Report 95 (IDR 95) by the ITER Joint Central Team (JCT).
dpa has been calculated for various zones of the First Wall (FW) and of the Shield Blanket (SB), where stainless steel is located. The second damage exposure index that has been considered and estimated is the gas production into the various ITER zones.
