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Second round of Launch Pad selections includes eight newcomers
The National Reactor Innovation Center at Idaho National Laboratory has announced 13 project selections across 12 companies for the Nuclear Energy Launch Pad, a Department of Energy–led program that integrates reactor and fuel facility authorization, testing, and deployment support for private nuclear developers.
The Launch Pad emerged from the Reactor Pilot Program and Fuel Line Pilot Program.
According to INL, projects selected include reactor development and nuclear fuel cycle advancements, including fabrication, enrichment, and conversion technologies.
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) | 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.