ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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!
Latest Magazine Issues
Dec 2024
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
January 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
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.
