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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
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.
Jiaqi Dong, Elena Montalvo, Rodolfo Carrera, Marshall N. Rosenbluth
Fusion Science and Technology | Volume 23 | Number 1 | January 1993 | Pages 42-50
Technical Paper | Plasma Engineering | doi.org/10.13182/FST93-A30118
Articles are hosted by Taylor and Francis Online.
The plasma vertical stability in a single-turn tokamak configuration is analyzed. The stabilization effects of the vacuum vessel and poloidal field magnet are studied numerically with rigid and magnetohydrodynamic models. An analytic mode dispersion relation is derived to estimate the effect of the single-turn toroidal field magnet on the plasma vertical stability. The typical growth time of the mode is found to be >1 s. The stability advantages of the single-turn configuration for a high-current tokamak plasma and the differences among the three models used are discussed. A single-turn tokamak configuration seems to be appropriate for a fusion ignition experiment in that it simplifies plasma control and makes feasible the control of high-current, elongated tokamak ignition plasma.
