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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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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Nuclear Science and Engineering
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Nuclear Technology
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.
R.A. Causey, K.L. Wilson, W.R Wampler, B.L. Doyle
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1585-1588
Material and Tritium | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29567
Articles are hosted by Taylor and Francis Online.
For the next generation of fusion reactors, tritium inventory will be one of the greatest safety concerns. Both CIT and ITER call for the use of graphite or carbon composites as the first wall and divertor material. If this graphite should contain a large number of traps for the storage of tritium, the resulting inventory could restrict the operation of the reactor. This report presents the results of an experimental study on the effects of neutron irradiation on the trapping of tritium in graphite. Enhancements in the trapping levels by two orders of magnitude up to as high as 0.2 atomic percent were seen for graphite samples irradiated to approximately 10 dpa at different temperatures. The results are compared to those obtained for ion damaged samples. The implications of the results for the operation of CIT and ITER are examined.
