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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.
T. R. Pinchback, J. R. Winkel, D. K. Matlock, D. L. Olson
Nuclear Technology | Volume 54 | Number 2 | August 1981 | Pages 201-207
Technical Paper | Material | doi.org/10.13182/NT81-A32735
Articles are hosted by Taylor and Francis Online.
The preliminary characterization of liquid rubidium attack on several alloys, which potentially will be used as construction materials for the 85Kr recovery hardware and storage cylinders, is presented. In the temperature range of 773 to 893 K, liquid rubidium attack on unstressed Type 304 stainless steel is shown to result in grain boundary attack and high temperature oxidation. It is shown to form several distinct temperature dependent corrosion layers. In the temperature range of 400 to 627 K, results from both stressed “C” rings and notched tensile tests submerged in liquid rubidium are presented for 6061 aluminum, AISI 4130 steel. Types 304 and 316 stainless steel, Monel 400, and Inconel 600. Monel 400 was identified as having a liquid-metal embrittlement susceptibility at 400 K.
