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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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.
S.L. Bogart, C.E. Wagner, N.A. Krall, S. Sedehi, C.F. Weggel, J.A. Dalessandro, T.J. Seed, K.O. Lund
Fusion Science and Technology | Volume 10 | Number 3 | November 1986 | Pages 1404-1411
Machine Upgrades and Next-Generation Device | doi.org/10.13182/FST86-A24925
Articles are hosted by Taylor and Francis Online.
The Demountable Toroidal Fusion Core (DTFC) concept has been analyzed for the Inductively Heated Tokamak (IHT), the Spherical Tokamak (ST), and the Reversed Field Pinch (RFP) for Fusion Engineering Research Facility (FERF) applications. Each of these confinement concepts is viewed as a “core” that is inserted into a surrounding machine envelope including, for example, the outboard toroidal field coil turns, the major poloidal equilibrium coils, blanket and materials testing stations, and a tension-suppression system (precompression) that provides mechanical integrity during the ignition and burn phases. Parametric systems analysis reveals that DTFC FERF operation is possible for all three confinement configurations with the IHT being the most costly and technologically challenging and the RFP being the least costly and, perhaps, least technologically challenging. Future work on the DTFC will be directed toward a Toroidal Physics Optimization Facility.