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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 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.
W. R. Fundamenski, A. A. Harms
Fusion Science and Technology | Volume 29 | Number 3 | May 1996 | Pages 313-349
Critical Review | Fusion Fuel Cycle | doi.org/10.13182/FST96-A30720
Articles are hosted by Taylor and Francis Online.
Advanced fuels for nuclear fusion — of which deuterium and 3He mixture is the leading candidate — could reduce tritium inventory, neutron fluence, structural damage, and activation in future reactors as well as allow for direct energy conversion. The feasibility of D-3He fusion is assessed based on recent developments in the areas of fuel resources, fusion and plasma physics, magnetic and inertial reactors, space propulsion, reactor safety, and waste disposal. It appears that D-3He fusion is not well suited to the conventional tokamak design (β ∼ 10%) because of excessive synchrotron loss and closed field topology. High-beta and/or non-Maxwellian plasma configurations are promising but at present lack a sufficient experimental database to predict reactor-relevant behavior. Space propulsion appears to be a most advantageous application of D-3He fusion.
