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
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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Nuclear Technology
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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.
Akira Yamaguchi, Hajime Niwa, Mitsuaki Yamaoka, Kazuyuki Tsukimori, Yoshio Shimakawa, Hisashi Ninokata, Kiyoto Aizawa
Nuclear Technology | Volume 107 | Number 1 | July 1994 | Pages 23-37
Technical Paper | Special on ANP ’92 Conference / Fission Reactor | doi.org/10.13182/NT94-A34995
Articles are hosted by Taylor and Francis Online.
Power Reactor and Nuclear Fuel Development Corporation (PNC), using computer codes developed and/or modified at PNC, has analyzed the Phase IIB passive safety test (PST) proposed for the Fast Flux Test Facility (FFTF). Major interests of PST are understanding core bowing and mitigating extremely low probability accidents. It is confirmed that the PNC code system is applicable to all aspects of the FFTF Phase IIB PST program. Results of the pretest analysis indicate that the proposed Phase IIB PST in FFTF can be devised to provide very useful data for validation of the analytical models that treat reactivity feedback effects due to core bowing. Recommendations to the test program are also made. With those analytical tools, future fast breeder reactor concepts will incorporate to a greater degree than earlier designs passive safety features on neutronic aspects as well as on thermohydraulic aspects.