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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
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!
Latest Magazine Issues
Apr 2025
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Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
May 2025
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.
Igor Kupriyanov, Nikolay Porezanov, George Nikolaev, Liudmila Kurbatova, Vyacheslav Podkovyrov, Anatoly Muzichenko, Anatoly Zhitlukhin, Yury Gasparyan, Alexander Gervash
Fusion Science and Technology | Volume 66 | Number 1 | July-August 2014 | Pages 171-179
Technical Paper | doi.org/10.13182/FST13-749
Articles are hosted by Taylor and Francis Online.
Beryllium will be used as a plasma-facing material for the ITER first wall. It is expected that erosion of beryllium under transient plasma loads such as the edge-localized modes (ELMs) and disruptions will determine the lifetime of the ITER first wall. The results of recent experiments with the Russian beryllium of TGP-56FW ITER grade on the QSPA-Be plasma gun facility are presented. The Be/CuCrZr mock-ups were tested by deuterium plasma and radiative streams both with pulse duration of 0.5 ms and heat loads of 0.5 and 0.4 MJ/m2, correspondingly. Experiments were performed at 250 °C. The beryllium mock-ups were exposed to up to 100 shots. After 10, 40 and 100 shots, the evolution of surface microstructure and crack morphology were investigated as well as beryllium mass loss under the erosion process. The deuterium retention in erosion products was also studied by the thermal desorption method.