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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.”
Keiji Miyazaki, Kensuke Konishi, Yoshihisa Gonno, Shoji Inoue, Masaki Saito
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 969-975
Blanket Technology | doi.org/10.13182/FST91-A29468
Articles are hosted by Taylor and Francis Online.
For reducing the liquid metal MHD pressure drop of the first wall cooling, a NaK experimental study was made on the effects of the electrical insulation of a rectangular duct. Three inner surfaces of a 2.1 mm thick 304-SS rectangular duct of 20.5 mm × 45.5 mm inner cross-section was coated by 1.3 mm thick FRP plates, remaining one of the 45.5 mm wide faces uninsulated to simulate the plasma facing first wall. The magnetic field was mainly applied in parallel to the uninsulated face. The results are summarized as follows. (1) The MHD pressure drop gradient is proportional to the mean flow velocity U and also to the magnetic flux density B. (2) It is about 2.3 times higher than the value predicted by Shercliff's theory for a completely insulated rectangular duct. (3) It is largely reduced, for the same velocity, down to 7.7% at B= 1.0 T and 5.1% at B= 1.5 T in comparison with the uninsulated duct. These results are encouraging for applying to fusion power reactors.