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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
Rainer P. Conrad, Cesare Merlini, Alfred-W. Mehner
Nuclear Technology | Volume 61 | Number 3 | June 1983 | Pages 403-415
Technical Paper | New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Nuclear Fuel | doi.org/10.13182/NT83-A33163
Articles are hosted by Taylor and Francis Online.
Advanced coated fuel particles doped with fission product and oxygen getters were screened for their mechanical irradiation performance compared to undoped reference-coated fuel particles of the highand low-enriched uranium cycle and the thorium/ high-enriched uranium cycle. The in-pile test was conducted under nominal and extreme operating conditions of current high-temperature gas-cooled reactor requirements. Doped coated fuel particles do not perform significantly better than reference particle systems; although, some advanced kernel varieties showed promising results.
