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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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 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.
Michael G. Izenson, Javier A. Valenzuela
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1828-1834
Plasma-Facing Component | doi.org/10.13182/FST92-A29984
Articles are hosted by Taylor and Francis Online.
Helium cooling offers safety advantages for fusion reactors because helium is single-phase and chemically inert. The Normal Flow Heat Exchanger (NFHX) enables highly efficient heat transfer to helium with low pressure drops at high heat fluxes. Thus, the NFHX enables helium cooling of divertor panels in Tokamak reactors and potentially enhances the safety of fusion power production. This paper explains the NFHX concept, presents the current status of the technology, and shows how the NFHX can be used to cool divertor panels in Tokamak reactors.
