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Division Spotlight
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.
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
May 2025
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.
E.T. Cheng, D.K. Sze, J.A. Sommers, O.T. Farmer III
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 2001-2008
Safety, Recycling, and Waste Management | doi.org/10.13182/FST92-A30015
Articles are hosted by Taylor and Francis Online.
Materials recycling aspects including contact gamma dose rates and cooling times were investigated for the first wall, blanket, and shield components of future fusion power reactors. Candidate structural mate-rials studied include ferritic steel, vanadium alloy, and SiC ceramic material. Required cooling times to reach hands-on recycling and impurity levels at given cooling times were estimated for the blanket components made of the various candidate structural materials. The relationship between the specific activity limits of radioactive materials for shallow-land burial (U.S. 10CFR61 Class C) waste disposal and the corresponding contact dose rates was examined. Scenarios for waste material management of fusion reactor components were suggested considering the materials recycling and shallow-land waste disposal options. Achievable impurity levels in vanadium ingot and titanium crystal bar were reviewed, and compared to desired levels for hands-on recycling. Methods to improve the purity levels were discussed.
