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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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 Science and Engineering
August 2024
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.”
Jean Boscary, Masanori Araki, Satoshi Suzuki, Koichiro Ezato, Masato Akiba
Fusion Science and Technology | Volume 35 | Number 3 | May 1999 | Pages 289-296
Technical Paper | doi.org/10.13182/FST99-A82
Articles are hosted by Taylor and Francis Online.
The purpose of the International Thermonuclear Experimental Reactor (ITER) divertor, which is located at the bottom of the vacuum vessel, is to exhaust impurities and their power from the plasma. Divertor plates function to withstand and to remove a steady-state surface heat flux of 5 MW/m2 and a transient peak heat flux up to 20 MW/m2 for 10 s on the side that faces the plasma. These demanding heat loads require active cooling by a pressurized subcooled flow of water as well as the development of a high-performance cooling channel to avoid burnout. Previous experiments showed that a screw tube, which is a tube whose inner surface is machined like a nut, is an efficient means of removing high heat fluxes. New experiments have been carried out with a B 0205 M10 type of screw copper tube. The average inner diameter, i.e., at the midheight of the fin, is 10 mm, and the outer diameter is 14 mm. Different pitches have been investigated: 1.5, 1.25, 1, and 0.75 mm. Incident critical heat fluxes (ICHFs) between 25 and 47 MW/m2 have been reached for local pressures ranging from 0.9 to 2.2 MPa, inlet temperatures from 17 to 33°C, and axial velocities from 3.6 to 14 m/s. ICHF increases as axial velocity increases and depends slightly on local pressure. Experimental results confirm the potentialities of the screw tube as a reliable geometry for fusion cooling tubes.