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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.
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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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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.
Alex Galperin, Yigal Ronen
Nuclear Technology | Volume 58 | Number 3 | September 1982 | Pages 388-396
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A32974
Articles are hosted by Taylor and Francis Online.
Received November 3, 1981 Accepted for Publication March 22, 1982 A symbiotic system of Pu-Th- and 233U-U-fueled reactors has been proposed and analyzed. The Pu-Th reactors utilize a tight lattice core and the 233U-U reactors utilize a regular pressurized water reactor (PWR) core. The two cases were investigated with different Pu-Th cores (system A: VM/VF =0.4 and system B: VM/VF - 1.0) and similar 233U-U cores. The cumulative 30-yr requirements of uranium ore and separative work for both systems were evaluated and indicated significant savings compared to current PWRs with plutonium recycle and the cross-progeny fuel cycle. The fuel cycle costs calculated for the proposed systems were slightly higher than those for the current PWR cycle.