KAERI (Korea Atomic Energy Research Institute) is developing an accelerator-driven transmutation system called HYPER (HYbrid Power Extraction Reactor). HYPER is the 1000MWth system designed to transmute the long-lived TRU (Transuranic Elements) and FP (Fission Product) included in the PWR spent fuel. LBE (Lead-Bismuth Eutectic) is used as the spallation target and coolant material in HYPER. KAERI has also investigated the conceptual design of a lead-cooled fast reactor. Lead (Pb) is used as the coolant material in that reactor. The most significant problem is a corrosion when using the lead-alloy liquid metal in those reactors. Therefore, it is necessary to study the corrosion characteristics and develop the technology to protect the steel structure materials against a corrosion. KAERI has been developing the facilities needed to study the corrosion of lead-alloy. KAERI fabricated a static corrosion test facility in 2003. The static corrosion tests of HT-9, 316L and T91 have been performed at 600 °C and 650 °C since 2003. The Pb-Bi loop was constructed in 2006. The Pb-Bi loop is an isothermal loop which can be operated at temperatures up to 550 °C. The Pb loop is designed to be operated with ΔT = 150 °C (Tmin = 450 °C and Tmax = 600 °C). The first stage of the Pb loop construction was finished and operations began in 2006. We will complete the second stage of the Pb loop construction after testing the first stage Pb loop.
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14th International Conference on Nuclear Engineering
July 17–20, 2006
Miami, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4242-8
PROCEEDINGS PAPER
The Lead-Alloy Corrosion Study at KAERI
Tae Yung Song,
Tae Yung Song
Korea Atomic Energy Research Institute, Daejeon, Korea
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Choonho Cho,
Choonho Cho
Korea Atomic Energy Research Institute, Daejeon, Korea
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Chungho Cho
Chungho Cho
Korea Atomic Energy Research Institute, Daejeon, Korea
Search for other works by this author on:
Tae Yung Song
Korea Atomic Energy Research Institute, Daejeon, Korea
Choonho Cho
Korea Atomic Energy Research Institute, Daejeon, Korea
Chungho Cho
Korea Atomic Energy Research Institute, Daejeon, Korea
Paper No:
ICONE14-89600, pp. 601-606; 6 pages
Published Online:
September 17, 2008
Citation
Song, TY, Cho, C, & Cho, C. "The Lead-Alloy Corrosion Study at KAERI." Proceedings of the 14th International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management. Miami, Florida, USA. July 17–20, 2006. pp. 601-606. ASME. https://doi.org/10.1115/ICONE14-89600
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