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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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
The 2025 ANS election results are in!
Spring marks the passing of the torch for American Nuclear Society leadership. During this election cycle, ANS members voted for the newest vice president/president-elect, treasurer, and six board of director positions (four U.S., one non-U.S., one student). New professional division leadership was also decided on in this election, which opened February 25 and closed April 15. About 21 percent of eligible members of the Society voted—a similar turnout to last year.
B. Zhao, B. H. Mills, S. I. Abdel-Khalik, M. Yoda
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 561-565
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST15-122
Articles are hosted by Taylor and Francis Online.
Three-dimensional numerical simulations of a test section modeling a single module of the helium-cooled modular divertor with multiple jets (HEMJ) design were performed to complement experimental studies at nearly prototypical conditions as part of the joint US-Japan effort on plasma-facing components evaluation by tritium plasma, heat, and neutron irradiation experiments (PHENIX). The Spalart-Allmaras turbulence model gave numerical predictions of the cooled surface temperature that were in good agreement with experimental estimates from a new helium loop. The simulations showed that spatial variations in incident heat flux, at least in the form of a Gaussian function, had a negligible effect on cooled surface temperatures.
Our initial results indicate that the numerical predictions of the thermal performance of a single HEMJ module are in reasonable agreement with the experimental studies. The simulations do, however, predict slightly higher heat transfer coefficients (HTCs) than the experimental studies, presumably because they do not account for thermal losses. The HTC appears to be essentially independent of incident heat flux, suggesting that the model can be used to investigate parameters that cannot be determined experimentally in many cases, such as the local HTC and temperature distributions within the divertor pressure boundary, at prototypical conditions.