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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
Jan 2025
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.
T. Nishitani, K. Kondo, S. Ohira, T. Yamanishi, M. Sugimoto, T. Hayashi, K. Ochiai
Fusion Science and Technology | Volume 68 | Number 2 | September 2015 | Pages 326-330
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST14-930
Articles are hosted by Taylor and Francis Online.
A neutron source for material and component tests is an essential tool for the DEMO reactor development. An accelerator-based neutron source such as IFMIF is regarded as the most promising one in Japan and the EU. The construction plan of IFMIF is still open due to the influence of the large cost overrun of ITER procurements. Japan Atomic Energy Agency (JAEA) has a plan of a neutron source for material and component tests using an IFMIF/EVEDA prototype accelerator and a lithium test loop for the IFMIF target facility. Expected performances of three options; 9 MeV and upgrading to 26 or 40 MeV of deuteron beam, are discussed. At the back plate position of the target, 1.5, 14, and 25 dpa/fpy are expected for 9, 26, and 40 MeV case, respectively. The option of 40 MeV is desirable, however, the option of 26 MeV is acceptable for blanket functional tests and material tests.
