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 Science and Engineering
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Nuclear Technology
Fusion Science and Technology
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.
Kazuyuki Takase, Tomoaki Kunugi, Yasushi Seki
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 1459-1464
Safety and Environment | doi.org/10.13182/FST96-A11963154
Articles are hosted by Taylor and Francis Online.
As one of thermofluid safety studies in ITER, buoyancy-driven exchange flow behavior through breaches of the vacuum vessel was investigated quantitatively using a preliminary LOVA (Loss Of VAcuum event) apparatus which simulated the Tokamak vacuum vessel of a fusion reactor with a small-scaled model. Helium gas and air were used as the working fluids. Experimental parameters were breach position, breach number, breach length, breach diameter, breach combination and the wall temperature of the VV. The present study showed that the relationship between the exchange rate and time depended on the magnitude of the potential energy from the ground level to the breach position and the wall temperature of the vacuum vessel. The exchange rate decreased as the breach length increased and the breach diameter decreased.