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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.
S. R. MacEwen, A. R. Causey
Nuclear Technology | Volume 44 | Number 1 | June 1979 | Pages 118-131
Technical Paper | Reactor | doi.org/10.13182/NT79-A32245
Articles are hosted by Taylor and Francis Online.
Irradiation creep and growth causes the core components in pressure tube reactors to change dimensions. The pressure tubes and calandria tubes in Canada Deuterium Uranium (CANDU) reactors elongate and may interact with the end shields. An analysis was performed that quantitatively describes the nature of this interaction. It is shown that as the fuel channels elongate, compressive stresses are induced in the pressure tubes, tensile stresses are induced in the calandria tubes, and the two end shields move apart. It is also demonstrated how simple mechanical adjustments can alter the nature of the induced stresses.