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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.
E. A. Mershad, W. W. Thomasson, J. J. Dauby
Nuclear Technology | Volume 32 | Number 1 | January 1977 | Pages 53-59
Technical Paper | Materials in Waste Storage / Radioactive Waste | doi.org/10.13182/NT77-A31737
Articles are hosted by Taylor and Francis Online.
An improved method for packaging tritiated waste water and oil for burial has been developed that significantly reduces tritium exposures to personnel and environment. The package uses current technology and relatively inexpensive materials to provide containment of the waste. Tests of the burial package indicate that the maximum tritium released during an 85-yr (7 half-lives of tritium) burial would be 0.002% of the total tritium contained in the package, or ∼1.4 Ci from the 70 000- Ci (2.59-PBq) (recommended maximum) package.
