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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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Nuclear Technology
Fusion Science and Technology
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.
A. Boltax
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1921-1926
Material and Tritium | doi.org/10.13182/FST92-A30000
Articles are hosted by Taylor and Francis Online.
During the late 1960s, the irradiation effects discoveries of void swelling, irradiation creep and loss of ductility of stainless steels created significant impacts on the design and development of fast breeder reactors. The Fast Flux Test Reactor (FFTF) was the first fast reactor to be designed subsequent to the initial quantification of these irradiation effects. This paper describes the experience of incorporating irradiation effects data in the design of the FFTF core restraint system and the evolutionary paths followed to develop the advanced materials in current use and under development.
