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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
May 2025
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.
C. E. Kessel
Fusion Science and Technology | Volume 15 | Number 2 | March 1989 | Pages 1015-1020
Magnet Engineering, Design and Experiments — II | doi.org/10.13182/FST89-A39826
Articles are hosted by Taylor and Francis Online.
A computational procedure is developed to include the structure in the determination of coil current and voltage trajectories to achieve a specified equilibrium evolution and drive the required plasma current. The method uses linear optimal control about a nominal trajectory determined without structure. Control of the gross equilibrium parameters R, Z, κ, δ, and Ip is covered. The analysis is done for the Compact Ignition Tokamak. This calculation can give more realistic time histories of coil currents and voltages, necessary in the accurate design of future tokamaks.