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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.
Richard N. Gurley, John A. Wethington, Jr.
Nuclear Technology | Volume 6 | Number 5 | May 1969 | Pages 483-493
Technical Papers and Note | doi.org/10.13182/NT69-A28325
Articles are hosted by Taylor and Francis Online.
The radiolysis of CF4, alone and mixed with UF6, UF6 + N2, UF6 + Ar, UF6 + Xe, UF6 + SF6, and UF4 + C by gamma photons from 60Co or by fission fragments from 235U gave C2F4 as the principal product. Traces of C2F6O and C3F3O were also found. In the gamma irradiation of CF4 + UF4 + C, charcoal acted as a fluorine scavenger and increased the consumption of CF4, but N2, Ar, Xe, and SF6 showed no measurable scavenging effects. During the fission fragment irradiations, C, N2, and Xe acted as scavengers, but such action by Ar or SF6 was not detected. The results for 60Co gamma irradiations and for fission fragment irradiations could be explained by a dynamic interconversion between CF4 and the products C2F4 and F2. A mathematical model that related the extent of interconversion with energy deposition was formulated.
