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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.
Shih-Jen Wang, Chun-Sheng Chien, Te-Chuan Wang
Nuclear Technology | Volume 126 | Number 1 | April 1999 | Pages 1-9
Technical Paper | Reactor Safety | doi.org/10.13182/NT99-A2954
Articles are hosted by Taylor and Francis Online.
The MELCOR code, developed by Sandia National Laboratories (SNL), is capable of simulating the severe accident phenomena of light water reactor nuclear power plants (NPPs).A specific station blackout accident (TMLB' sequence) for Maanshan NPP is simulated using the MELCOR 1.8.3 code. The MELCOR input deck for Maanshan NPP is established based on Maanshan NPP design data and the MELCOR users' guides. The initial steady-state conditions are generated with a developed self-initialization algorithm. The main severe accident phenomena and the corresponding fission product release fractions associated with the TMLB' sequence were simulated. The sequence of events up to the vessel breach is similar to that in the SNL report simulated with MELCOR 1.8.2. The predicted results provide useful information for the probabilistic risk assessment (PRA) of Maanshan NPP. This tool will be applied to the PRA, the severe accident analysis, and the severe accident management study of Maanshan NPP in the near future.
