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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
Lightbridge announces first U-Zr fuel rod samples extruded at INL
Lightbridge Corporation announced today that it has reached “a critical milestone” in the development of its extruded solid fuel technology. Coupon samples using an alloy of zirconium and depleted uranium—not the high-assay low-enriched uranium (HALEU) that Lightbridge plans to use to manufacture its fuel for the commercial market—were extruded at Idaho National Laboratory’s Materials and Fuels Complex.
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.