Since very high temperature gas-cooled reactor (VHTR) components for a hydrogen production are designed for a lifetime of 30 to 60 years at a high-temperature of 950°C, a material selection is important, and also one of the most important properties in these metallic components is their longterm creep behavior. In this study, for selecting a suitable material for the intermediate heat exchanger (IHX), the hightemperature strengths of several candidate alloys approved for use by ASME VIII (boiler and pressure vessel code) were reviewed. From this review, alloy 617 was immediately selected as one of the best materials. In addition, to provide design data for a long duration for alloy 617, lots of creep data was collected through world-wide literature surveys of European Alloy-DB and available literature surveys. Using these data, a long-term creep life for alloy 617 was predicted for up to 106 hours based on the Larson-Miller (LM) parameter. Also, the creep rupture data was analyzed by a statistical treatment. Creep master curves for the creep-life prediction were presented for various standard deviations; 1σ, 1.65σ, 2σ and 3σ. A minimum design value for the creep-rupture time was found to be 10 times lower than the average value. Failure probability of the creep rupture data followed a lognormal distribution well.
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ASME 2007 Pressure Vessels and Piping Conference
July 22–26, 2007
San Antonio, Texas, USA
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
0-7918-4287-8
PROCEEDINGS PAPER
Analysis of the Creep Rupture Data of Alloy 617 for a High Temperature Gas Cooled Reactor
Woo Gon Kim,
Woo Gon Kim
Korea Atomic Energy Research Institute, Daejeon, South Korea
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Song Nan Yin,
Song Nan Yin
Korea Atomic Energy Research Institute, Daejeon, South Korea
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Woo Seog Ryu,
Woo Seog Ryu
Korea Atomic Energy Research Institute, Daejeon, South Korea
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Jong Hwa Jang
Jong Hwa Jang
Korea Atomic Energy Research Institute, Daejeon, South Korea
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Woo Gon Kim
Korea Atomic Energy Research Institute, Daejeon, South Korea
Song Nan Yin
Korea Atomic Energy Research Institute, Daejeon, South Korea
Woo Seog Ryu
Korea Atomic Energy Research Institute, Daejeon, South Korea
Jong Hwa Jang
Korea Atomic Energy Research Institute, Daejeon, South Korea
Paper No:
CREEP2007-26834, pp. 439-444; 6 pages
Published Online:
August 20, 2009
Citation
Kim, WG, Yin, SN, Ryu, WS, & Jang, JH. "Analysis of the Creep Rupture Data of Alloy 617 for a High Temperature Gas Cooled Reactor." Proceedings of the ASME 2007 Pressure Vessels and Piping Conference. Volume 9: Eighth International Conference on Creep and Fatigue at Elevated Temperatures. San Antonio, Texas, USA. July 22–26, 2007. pp. 439-444. ASME. https://doi.org/10.1115/CREEP2007-26834
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