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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.
Constantine P. Tzanos
Nuclear Technology | Volume 82 | Number 1 | July 1988 | Pages 5-17
Technical Paper | Fission Reactor | doi.org/10.13182/NT88-A34113
Articles are hosted by Taylor and Francis Online.
A method was developed for the analysis of a once-through steam generator that is based on a multinode movable boundary formulation and an accurate description of the departure from nucleate boiling boundary. In the development of this method, a liquid-metal reactor steam generator was used as a reference design. To evaluate its performance, the Energy Technology Engineering Center steam generator shutdown experiment in the once-through mode was analyzed. Also, the predictions of this method were compared with those of another steam generator code. These analyses showed that the predictions of this methodology agree very well with the experimental measurements and the predictions of the other code. The maximum difference between the temperatures predicted by this model and measurements was ∼5 K.
