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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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.
S. Stoenescu, T. Feng, J. Swanson
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1127-1132
Ignition Device | doi.org/10.13182/FST91-A29494
Articles are hosted by Taylor and Francis Online.
An essential support system of the Compact Ignition Tokamak (CIT) is the Vacuum Vessel Heating/Cooling (H/C) System. The requirement for the design of the dual function H/C System is to initially provide sufficient input heat energy to raise the temperature of the vacuum vessel from a 21°C ambient temperature to the operating temperature of 340±10°C and subsequently provide sufficient heat removal capacity to limit the cooling period between plasma pulses to 1 hour. The H/C System currently proposed for the CIT vacuum vessel accomplishes both of these system objectives using a single gaseous helium system flowing through a series of ducts attached to the exterior surface of the vacuum vessel shell. The design requirements, duct arrangements, and design analyses for the preliminary H/C System design are identified.
