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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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
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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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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.
J.N. Brooks†, M. Kaminsky††
Fusion Science and Technology | Volume 6 | Number 2 | September 1984 | Pages 465-474
Technical Paper | Selected papers from the Ninth International Vacuum Congress and the Fifth International Conference on Solid Surfaces (Madrid, Spain, September 26-October 1, 1983) | doi.org/10.13182/FST84-A23223
Articles are hosted by Taylor and Francis Online.
A REDEP computer-code-analysis has been performed for the transport, ionization, and redeposition of physically sputtered material in the boundary regions of the FED/INTOR tokamak. The analysis was performed for TiC as a candidate coating material for the bottom limiter and the divertor plate. This analysis provides the first assessment of the influence of preferential sputtering of TiC on sputter erosion and redeposition. The results indicate that at high edge temperatures, the different transport properties of the constituents causes significant differences in both the erosion and redeposition rates for the elemental constituents carbon and titanium. At low plasma edge temperatures, ≲ 50 eV, TiC is marginally acceptable, having a high gross erosion rate but a fairly low net rate.