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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.
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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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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.
W.T. Shmayda, N.P. Kherani, B. Wallace†, F. Mazza‡
Fusion Science and Technology | Volume 21 | Number 2 | March 1992 | Pages 616-621
Safety; Measurement and Accountability; Operation and Maintenance; Application | doi.org/10.13182/FST92-A29816
Articles are hosted by Taylor and Francis Online.
St 198 alloy is attractive for glovebox clean-up systems operating with nitrogen cover gases, offering good tolerance to impurities which may permeate into the box from the environment and stable sorption speeds for alloy loadings as high as 360 mCi/g. At this loading the tritium concentration in the stream leaving the scavenger bed will be of the order of 400 µCi/m3. The alloy operating conditions can be adjusted to increase the quantity of tritium stored in the alloy or to reduce the tritium concentration in the effluent. Methane can not be removed from a nitrogen stream with St 198. A glovebox clean-up system based on the use of this alloy is under evaluation.
