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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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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.
Thomas S. Drolet, Kam Yuen Wong, Paul J. C. Dinner
Fusion Science and Technology | Volume 5 | Number 1 | January 1984 | Pages 17-29
Technical Paper | Special Section Contents / Tritium System | doi.org/10.13182/FST84-A23074
Articles are hosted by Taylor and Francis Online.
Fusion power stations using the deuterium-tritium reaction will have substantial inventories of tritium in the oxide, molecular, and solid (metal hydride) forms. A new Canadian fusion engineering project based on Canada deuterium uranium (CANDU) operating experience with deuterium and tritium and plans to extract and concentrate tritium from Ontario Hydro's reactors is described. The aims of this project are to contribute to the international fusion effort by extracting useful existing information and translating that experience for application to fusion, and acting as a technology development agency by funding further research and development (R&D) in project mandate areas. Project R&D activities in each of the following five mandate areas are described: 1. Fuel Systems and Tritium Management Programs 2. Materials Technology Programs 3. Equipment Development Programs (including remote operations) 4. Health and Environmental Program 5. Breeding Blanket Technology Program. Also summarized are health and safety experiences with tritium in the CANDU program and plans for large-scale tritium removal from heavy water moderator and coolant systems.
