ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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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May 2025
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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.
T. H. Pigford, C. S. Yang, M. Maeda
Nuclear Technology | Volume 41 | Number 1 | November 1978 | Pages 46-59
Technical Paper | Fuel Cycle | doi.org/10.13182/NT78-A32132
Articles are hosted by Taylor and Francis Online.
Fuel cycles are examined that utilize dispersed national reactors fueled with uranium denatured by diluting the fissile uranium with 238U. Discharged fuel is to be stored or is to be reprocessed in an international center, where the recovered plutonium is to be consumed in a plutonium-burner reactor. Material quantities are calculated for national pressurized water reactors (PWRs) or heavy water reactors (HWRs) exchanging fissile material with international PWRs or liquid-metal fast breeder reactors. The national reactors are fueled with low-enrichment uranium or with denatured uranium and thorium. The plutonium-burner reactors are fueled with plutonium and natural uranium or plutonium and thorium. The greater ratio of power of national reactors to the power of the plutonium-burning reactors occurs for national HWRs fueled with uranium and thorium and for international reactors fueled with plutonium and thorium. The vulnerability of denatured uranium to further enrichment and the complexity of reprocessing, refabrication, and enrichment operations at the international center are analyzed. PWRs and high-temperature gas-cooled reactors fueled with denatured uranium and operating without fuel reprocessing are also considered.