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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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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.
L. W. Lang
Nuclear Technology | Volume 9 | Number 2 | August 1970 | Pages 242-249
Economic | Symposium on Theoretical Models for Predicting In-Reactor Performance of Fuel and Cladding Material | doi.org/10.13182/NT70-A28813
Articles are hosted by Taylor and Francis Online.
The power costs of three hypothetical reactor sites are analyzed to compare the site costs of conventionally fueled fast and thermal reactors with thorium-blanketed breeders and 233U fueled light-water reactors (LWR's). Since the most critical parameter is time, three case variations are considered. The site start-up is considered coincident with the commercial introduction of the fast reactor; and alternatively, where site start-up occurs jive and ten years after the commercial introduction of the breeder. The cost comparisons also consider the effect of U3O8 price increases. The value of 233U produced by thorium-blanketed breeders exceeds that of the Pu produced by 238U blanketed breeders. Since the power costs of the LWR's are lower than the breeders until the price of U3O8 increases, early development of the breeders may be contingent upon implementation of the crossed-progeny fueling.