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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!
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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
T. Kawabe, S. Hirayama, Y. Kozaki, K. Yoshikawa, N. Asami, Y. Fukai, K. Hattori, H. Hojo, T. Honda, H. Ida, T. Kitajima, S. Koda, K. Komatsu, R. Kumazawa, F. Matsuoka, T. Miyasugi, N. Morino, H. Nakashima, H. Nakata, S. Sato, Y. Uede, T. Watanabe, M. Yamada, Y. Yamamoto, H. Yamato
Fusion Science and Technology | Volume 10 | Number 3 | November 1986 | Pages 1102-1110
Nuclear Technology Experiments and Facilities | doi.org/10.13182/FST86-A24880
Articles are hosted by Taylor and Francis Online.
Conceptual design study of 14-MeV neutron source (FEF) of compact DT plasma based on the mirror confinement has been carried out to clarify the critical issues both in plasma physics and engineering. Characteristic feature of FEF-II are (i) use of RF pondermotive force for MHD stability, (ii) use of water for radiation shield of SC coil and (iii) use of end electrode system including plasma direct energy conversion. Several sets of plasma parameters are obtained under the variety of conditions from the most pessimistic case where the charge exchange (CX) loss of ions is dominant to the most optimistic case where the CX loss is negligible. The engineering feasibility has been studied for the pessimistic case. It was found that most of the engineering are feasible in the optimistic case, and that even in the pessimistic case by increasing plasma parameters there is possibility to meet engineering requirement.
