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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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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 Technology
Fusion Science and Technology
Latest News
Vogtle-3 shuts down for valve issue
One of the new Vogtle units in Georgia was shut down unexpectedly on Monday last week for a valve issue that has since been investigated and repaired. According to multiple local news outlets, Georgia Power reported on July 17 that Unit 3 was back in service.
Southern Company spokesperson Jacob Hawkins confirmed that Vogtle-3 went off line at 9:25 p.m. local time on July 8 “due to lowering water levels in the steam generators caused by a valve issue on one of the three main feedwater pumps.”
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.