ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
November 2024
Nuclear Technology
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Fusion Science and Technology
Latest News
Tank waste operations resume at Idaho’s IWTU
The Department of Energy’s Office of Environmental Management announced yesterday that waste processing operations have resumed at the Integrated Waste Treatment Unit (IWTU) at the Idaho National Laboratory Site. The resumption of operations follows the completion of two maintenance campaigns at the radioactive liquid waste treatment facility.
Kenzo Ibano, Yasushi Yamamoto, Satoshi Konishi
Fusion Science and Technology | Volume 60 | Number 1 | July 2011 | Pages 243-246
Divertor & High Heat Flux Components | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1) | doi.org/10.13182/FST11-A12360
Articles are hosted by Taylor and Francis Online.
Plasma parameters for a low-Q tokamak reactor GNOME were studied to meet the allowable heat load constraints of the divertor component. EQLAUS/ERATO codes and DRIVER88 codes were used for the core plasma models to determine the power flux into SOL regions for this calculation. Then, the heat flux to the divertor plate was estimated with a parameter of the radiation power at SOL/divertor regions. A simple Core-SOL-Divertor (C-S-D) model has been used for this purpose. Finally, three operation regions with the required radiation power to meet the allowable peak heat load were proposed.