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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.
Satoshi Nishio, Kichiro Shinya
Fusion Science and Technology | Volume 19 | Number 1 | January 1991 | Pages 86-94
Technical Paper | Plasma Engineering | doi.org/10.13182/FST91-A29318
Articles are hosted by Taylor and Francis Online.
A new method for mapping the plasma operational space of a tokamak reactor is proposed. The operational space within poloidal field (PF) coil engineering constraints is defined by three parameters, ψ, βp, and Ip, which are the magnetic flux supplied by the PF coil system, the poloidal beta, and the plasma current, respectively. It is also shown that the boundaries of the plasma operational space have a one-to-one correspondence with the PF coils. The design specifications of the PF coil system are thus related to the plasma operational space.