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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.
Kurt Borrass, William R. Spears
Fusion Science and Technology | Volume 14 | Number 1 | July 1988 | Pages 228-245
Technical Paper | Net Overview | doi.org/10.13182/FST88-A25161
Articles are hosted by Taylor and Francis Online.
Scoping studies for the Next European Torus (NET) using the SUPERCOIL system code are described. Capital-cost-optimized devices satisfying constraints imposed on stresses/strains, fields, access, etc., are compared. The main objective is to determine the impact of design characteristics, performance objectives, and underlying plasma physics assumptions on the parameters and cost of NET. The background against which the main parameters of NET have been chosen is developed and illustrated by the NET study points used during the conceptual design phase. Supporting studies extrapolating NET design and physics assumptions to DEMO and power reactors are performed to allow the reactor relevance of the physics performance and testing program of NET to be justified.