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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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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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 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. 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.”
Giovanni Dell'Orco, Warren Curd, Fabien Berruyer, Seokho Kim, Roy Shearin, Juan Ferrada
Fusion Science and Technology | Volume 60 | Number 1 | July 2011 | Pages 100-104
ITER Systems | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1) | doi.org/10.13182/FST11-A12334
Articles are hosted by Taylor and Francis Online.
ITER is a joint international fusion facility to demonstrate the scientific and technological feasibility of fusion power for future commercial electric power facilities. ITER is designed to reject all the heat generated in the plasma and transmitted to the in-vessel components through the Tokamak Cooling Water System (TCWS) to the intermediate closed loop Component Cooling Water System (CCWS) and then to the environment via the open Heat Rejection System (HRS) and Cooling Towers. At the present the main in-vessel components as First Wall-Blanket (FW-BLK) and the Divertor (DIV) are cooled via four separated Primary Heat Transfer Systems (PHTSs). This paper describes the proposal to integrate the PHTS for the FW-BLK and DIV in a common loop to improve the availability and reliability of the cooling system. Furthermore, the paper presents the new thermal hydraulic design parameters, the relevant Process Flow Diagram (PFD) and a study for the new arrangements of the piping in the TCWS vault. Some associated issues for safety accidental scenarios are planned to be solved before the final acceptance of the proposal in the baseline design.