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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.
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2021 Student Conference
April 8–10, 2021
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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
Ohio Senate votes to repeal nuclear plant subsidies
After months of unsuccessful efforts by Ohio lawmakers to contend with the fallout from H.B. 6—the now-infamous nuclear subsidies bill signed into law in 2019—the state’s senate on March 3 passed a measure, S.B. 44, to repeal those subsidies. The vote was 32–0.
For those who may need reminding, federal prosecutors on July 21, 2020, arrested Larry Householder, then speaker of the Ohio House, and four lobbyists and political consultants for their involvement in an alleged $61 million corruption and racketeering scheme aimed at guaranteeing passage of H.B. 6, whose subsidies had kept Ohio’s Davis-Besse and Perry nuclear power plants from premature closure.
H.B. 6 established a seven-year program to charge the state’s electricity consumers fees to support payments of about $150 million annually to the plants’ operator, Energy Harbor Corporation, then known as FirstEnergy Solutions (FES). FES had announced in March 2018 that it would be forced to close Davis-Besse and Perry without some form of support from the state. (The payments to Energy Harbor were blocked last December by an Ohio Supreme Court injunction, which complemented an earlier lower court ruling.)
Young-Dug Bae, Suk-Kwon Kim, Dong-Won Lee, Bong-Guen Hong
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 91-95
Divertor and High Heat Flux Components | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | dx.doi.org/10.13182/FST09-A8882
Articles are hosted by Taylor and Francis Online.
A high heat flux test facility using a graphite heating panel was constructed and is presently in operation at Korea Atomic Energy Research Institute, which is called KoHLT-1. One of the major purposes of this facility is to carry out a thermal cycle test of the ITER (International Thermonuclear Experimental Reactor) FWQM (first wall qualification mockup). The facility is equipped with a graphite heating element, a water cooled box-type vacuum chamber, and diagnostic systems. Two mockups are installed in the chamber; two facing mockups are simultaneously heated by a graphite heater installed between two mockups. The graphite heating element has an effective irradiation area of 244 mm × 80 mm and its electrical power is provided by a 40 kW DC power supply. The diagnostic system consists of two independent calorimetric power measuring systems, thermocouples, a vacuum gauge, and a CCD camera. Water cooling, Be treatment, and vacuum pumping systems are also equipped. We performed thermal cycle tests for two Cu mockups, and for Cu and Cu/SS mockups ensure the performance of the KoHLT-1. After that, we carried out thermal cycle tests up to 220 cycles for Cu mockup and FWQM at 0.65 MW/m2, from which the reliability of the KoHLT-1 was verified.
