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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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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.”
Kenzo Munakata, Teruki Fukumatsu, Satoshi Odoi, Masabumi Nishikawa
Fusion Science and Technology | Volume 33 | Number 4 | July 1998 | Pages 435-442
Technical Paper | doi.org/10.13182/FST98-A42
Articles are hosted by Taylor and Francis Online.
Catalytic oxidation and adsorption comprise the most conventional and reliable method for removing tritium that is accidentally released into the working area of fusion power plants. Based on both hot and cold experimental databases, a numerical calculation code with the temporary name TRITON QUEST is being developed to support the design of the air cleanup system. The code has been considerably improved in terms of mass balance equations and calculation method. It has also become possible to conduct larger-scale computations in which catalyst or adsorption beds of actual scale are used. The behavior of tritium in the case of an accidental release of 100 g of tritium in the International Thermonuclear Experimental Reactor (ITER) test plant was predicted using this numerical computation code. The results of numerical computation indicate that the tritium concentration in a room with a volume of 10 000 m3 can be reduced to the regulatory level within 24 h when an air cleanup system with 1000 kg of Pt/alumina catalyst and 2500 kg of MS5A is operated with a ventilation rate of 10 000 m3/h. The decontamination efficiency for new arrangements of the air cleanup system was also investigated. The results suggest that the new arrangements have an advantage in the regeneration of the air cleanup system.