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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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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.
W. Schenk, A. Naoumidis
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 228-233
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-A32321
Articles are hosted by Taylor and Francis Online.
In the course of the German high-temperature gas-cooled reactor Prototype Nuclear Process Heat Safety Program, the behavior of unirradiated fuel particles as well as of irradiated fuel elements at high temperatures was investigated. Unirradiated fuel particles with different designs have been heated to temperatures of 2500°C. Different particle types showed a different high-temperature behavior. While the Biso Thorium High-Temperature Reactor (THTR) type was the most resistant one, Triso particles failed at lower temperatures because of the SiC decomposition. Whole fuel spheres with Biso particles, irradiated in a pebble-bed reactor, were also heated up to 2500°C THTR fuel elements with a burnup of 12 to 16% FIMA (120 000 to 160 000 MWd/t) showed excellent behavior up to 2400°C. At 2500°C, the particles failed in significant numbers after some hours. While rare gas nuclides and iodine were retained in the coated particles as long as the coatings remained intact, the release of some solid fission products, especially cesium, was high above 2000°C.