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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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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.
Y. Nakao, T. Honda, Y. Honda, K. Kudo, H. Nakashima, M. Ohta
Fusion Science and Technology | Volume 20 | Number 4 | December 1991 | Pages 824-828
Inertial Confinement Fusion | doi.org/10.13182/FST91-A11946943
Articles are hosted by Taylor and Francis Online.
A chain-like process of knock-on and suprathermal fusion events due to the introduction of a primary 14-MeV neutron is examined, on the basis of transport equations for neutrons and recoil ions of all possible generations. In reactor-grade DT pellets, the ratio of suprathermal-fusion to primary 14-MeV neutrons becomes 0.1 or more. The maximum energy of neutrons leaking out of the pellet surface reaches to 45 MeV, though the population above 30 MeV is negligibly small.