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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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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.
Masami Ohnishi
Fusion Science and Technology | Volume 2 | Number 4 | October 1982 | Pages 609-616
Technical Paper | Plasma Engineering | doi.org/10.13182/FST82-A20801
Articles are hosted by Taylor and Francis Online.
Since an ignited deuterium-tritium plasma of a moving ring compact torus reactor (MRCTR) is thermally unstable at the operating temperature, suppression of the thermal instability is an essential issue for maintaining the stationary burning of a plasma. The feedback stabilization by means of major radial compression-decompression is proposed for a burn control in an MRCTR. The compression-decompression is carried out through the regulation of the solenoidal magnetic field according to the deviation of the ion temperature from the equilibrium value. The dynamics of a plasma core with a feedback control is calculated in a zero-dimensional plasma model assuming the empirical confinement scalings obtained in the present tokamak experiments. The effects of ion density on the dynamics are also studied for two extreme cases of complete particle recycling and perfect pumping. The scheme is found to be effective for the burn control. The deviations of a major radius and a fusion output power are less than several percents of the equilibrium values during the control to suppress the temperature excursion. The rate of change in the magnetic field for the control is as slow as 500 G/s.