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.
Explore membership for yourself or for your organization.
Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
Jul 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
August 2025
Nuclear Technology
Fusion Science and Technology
July 2025
Latest News
DOE issues new NEPA rule and procedures—and accelerates DOME reactor testing
Meeting a deadline set in President Trump’s May 23 executive order “Reforming Nuclear Reactor Testing at the Department of Energy,” the DOE on June 30 updated information on its National Environmental Policy Act (NEPA) rulemaking and implementation procedures and published on its website an interim final rule that rescinds existing regulations alongside new implementing procedures.
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.