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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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.
Carol A. Sege, Saul Strauch, Ronald P. Omberg, Irving Spiewak
Nuclear Technology | Volume 42 | Number 2 | February 1979 | Pages 144-149
Technical Paper | Thorium Fuel Cycle in a Breeder Economy / Reactor | doi.org/10.13182/NT79-A32144
Articles are hosted by Taylor and Francis Online.
We performed a scenario evaluation that delineates the potential role of denatured uranium/ thorium-fueled reactors, including breeders, in symbiotic systems. In this study, reactors fueled with plutonium were built in secure centers, while reactors at dispersed sites were fueled with natural, lowenriched, or denatured uranium (12% 233U or 20% 235U in 238 U) The installed nuclear capacity is assumed to be 350 MW(electric) in the year 2000, with a net increase of 15 GW(electric)/yr permitted through the year 2050. The U.S. Department of Energy Division of Uranium Resources and Enrichment projected the two bounding cases of uranium recoverable at a marginal cost of $160/lb U3O8 or less used in this study. The marginal cost of $160/lb U3O8 occurs at 3 million short tons (ST) for the high-cost supply and at 6 million ST for the intermediate-cost supply. For the assumed high-cost U3O8 supply (3 million ST U3O8), thermal recycle with denatured light water reactors (LWRs) will achieve the same incremental increase in maximum achievable nuclear capacity as U/Pu recycle in LWRs [∼200 GW(electric) more than once-through cycles]. Introduction of a breeder is required for the system to achieve the projected nuclear demand [1100 GW(electric) in 2049]. For all denatured systems, including those with breeders, a significantly larger fraction of the installed capacity can be located at dispersed sites, compared with U/Pu systems. For the assumed intermediate-cost U3O8 supply (6 million ST U3O8), thermal recycle with advanced converters will permit projected nuclear demand to be met for both the Pu/U and denatured uranium-thorium cycles.