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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.
G. R. Kirkland, E. R. Davies, M. E. Lambert
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 470-478
Technical Paper | Materials | doi.org/10.13182/NT55-478
Articles are hosted by Taylor and Francis Online.
During commissioning of the Dounreay prototype fast reactor steam generators in 1974, a steam-to-sodium leak occurred in the tube-to-tube-plate weld area in one of three superheaters. This caused caustic stress corrosion of the tube plate in the areas exposed to the products of the sodium-water reaction. Metallurgical examination of several welds revealed one manufacturing defect, which was due to reheat cracking. This was the likely cause of the initial steam-to-sodium leak that resulted in failure in several adjacent tubes due to caustic stress corrosion cracking. The holes in the tube plate where the welds had been cut out for examination were plugged by explosive welding techniques and the unit returned to service.