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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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.”
Jun Soo Lee, Dong Won Lee, Goon Cherl Park
Fusion Science and Technology | Volume 60 | Number 2 | August 2011 | Pages 544-548
Blanket Design and Experiments | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 2) | doi.org/10.13182/FST11-A12439
Articles are hosted by Taylor and Francis Online.
Through consideration of the requirements for a DEMO-relevant blanket concept, Korea (KO) has proposed a He-Cooled Molten Lithium (HCML) Test Blanket Module (TBM) for testing in the International Thermonuclear Experimental Reactor (ITER). To validate the safety of the HCML TBM design concept and guarantee high efficiency of the power conversion system, an evaluation of the heat transfer capability of the gas coolant in a high Reynolds number regime should precede this test. In this study, a thermal hydraulic test with a high-pressure nitrogen gas loop was performed and a thermal hydraulic analysis was carried out with the commercial CFD code Fluent 6.3.26 and the system code GAMMA (Gas Multicomponent Mixture Analysis) under the same test conditions. In the experiment, a single TBM First Wall (FW) mock-up made from the same material as the KO TBM, ferritic martensitic steel, was used, and the test was performed at pressures of 11, 19 and 29 bar and under various flow rates ranging from 0.63 to 2.44 kg/min. As one-side of the mock-up was heated by a furnace heater at a constant temperature, the wall temperatures were measured by installed thermocouples, with the measured temperatures showing strong parity with code results simulated under the same test conditions. Even with the system code using the modified Dittus-Boelter correlation, which was developed under a different heating condition, the three-dimensional approach of the system code is capable of estimating a one-sided heating condition in a fusion application.