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Division Spotlight
Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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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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.
H.U. Borgstedt, M. Grundmann, J. Konys
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 536-540
Material Engineering — Behavior | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A40094
Articles are hosted by Taylor and Francis Online.
Liquid lithium, which is under consideration as blanket fluid of fusion reactors, is more corrosive against austenitic and martensitic-ferritic steels than liquid sodium. The results of corrosion studies in flowing lithium as well as of tests on the mechanical behaviour of the materials in stagnant lithium at 550°C are presented and discussed. The candidate materials are nearly insensitive against liquid metal embrittlement in lithium at 200 to 250°C. After precorrosion in lithium at 550°C, they show more or less brittle fracture behavior in lithium of 200 to 250°C.