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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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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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.
T. Satake, M. Hashiba, M. Mohri, T. Yamashina, N. Ohsako, Y. Hayashi
Fusion Science and Technology | Volume 6 | Number 2 | September 1984 | Pages 511-515
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-A23229
Articles are hosted by Taylor and Francis Online.
A fundamental study of cryopumping of a charcoal sorption panel with a refrigerator was performed aimed at applications in nuclear fusion experiments. Typical pumping speeds at the cryopanel temperature of 10.4 K for hydrogen, helium and argon were obtained as 3.5 × 10−1, 1.6 × 10−2 and 1.0 m3/s, respectively, in the range of throughput less than 1 × 10−4 Pa ·m3/s. The pumping speed was found to increase linearly on a semilogarithmic plots with the inverse of adsorption temperature. The activation energy of hydrogen capture on the charcoal was estimated between 100 J/mol to 240 J/mol, which is nearly equal to the heat of fusion of hydrogen. Several experiments to improve cryopumping performance were also carried out by modification of the shape of the cryopanel, and by evaporation of titanium onto the panel and etc.