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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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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.
Ikuhide Tokami, Masataka Nakahira, Satoshi Sato, Kazuyuki Furuya, Toshihisa Hatano, Toshimasa Kuroda, Hideyuki Takatsu
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 574-578
International Thermonuclear Experimental Reactor | doi.org/10.13182/FST96-A11963000
Articles are hosted by Taylor and Francis Online.
A modular blanket has been proposed for a fusion experimental reactor, such as ITER, to enhance its maintainability as well as improve its fablicability. The blanket module is connected to a strong back plate via support legs protruded from both of the module and the back plate. A welding approach has been investigated for the joining of the support leg that is 70 mm thick to withstand electromagnetic forces and with limited welding/cutting heads working space of 100 mm × 150 mm adjacent to the support leg.
After comparison of several methods, e.g. NGTIG, NGMIG and iodine laser, NGTIG has been selected as a reference for welding and plasma cutting for cutting. Iodine laser has been chosen as an alternative for both of welding and cutting. Through preliminary design studies, the possibility of small welding/cutting heads including their driving systems available to the limited space has been shown. Maintenance route for in-situ module replacement with temporary fixture jigs has been also investigated.