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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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.
J.M. Perlado, J. Sanz,a D. Guerra, A.S. Perez
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 709-715
Inertial Fusion | doi.org/10.13182/FST91-A29428
Articles are hosted by Taylor and Francis Online.
The feasibility of the ferritic alloy HT-9 as the main component of the first structural wall (FSW) of inertial confinement fusion (ICF) reactors, such as HIBALL-II or LIBRA, which use thin film liquid protection through porous tubes (INPORT) has been studied in terms of radiation damage and activation. Swelling and shift in the ductile brittle transition temperature (DBTT) have been analyzed in the light of the results of experimental fast breeder reactors, which are demonstrated to be good experimental tools in our ICF range. The good performance of HT-9 is remarkable. An analysis of the generation of new solid transmutants and the depletion of initial constituents is given. Activation has been studied using recycling and shallow land burial (SLB) criteria. The interest has been focussed in a reduced activation HT-9 (Niobium-free). Recycling using HT-9 is shown to be not feasible. SLB waste disposal is also not feasible. The critical role of some short lived isotopes as Pt193, Nb93m, Re186 is analyzed, together with that of the more conventional Re186m, Nb94, Bi210m.
