The very high temperature reactor (VHTR) materials R&D started as an objective of the development of key technologies for a nuclear hydrogen production funded by the Korea government in 2006. We are performing materials R&D for 5 components: a reactor pressure vessel (RPV), a reactor/process intermediate heat exchanger (IHX) and hot gas duct, a control rods component, a reflector and support structures in the core region and reactor materials for the sulfur-iodine (SI) process. The scopes of our works are focused on a material screening/selection and qualification, codifications of a high temperature structural design to a very high temperature region, and to support the licensing of a system design, material characterizations and database establishments. Current target materials are modified 9Cr-1Mo, alloy 617, graphite, ceramic fiber reinforced composite, Fe-Si and SiC.
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Fourth International Topical Meeting on High Temperature Reactor Technology
September 28–October 1, 2008
Washington, DC, USA
Conference Sponsors:
- ASME
ISBN:
978-0-7918-4855-5
PROCEEDINGS PAPER
Development of Materials for a High Temperature Gas Cooled Reactor in Korea
Ji Yeon Park,
Ji Yeon Park
Korea Atomic Energy Research Institute, Daejeon, South Korea
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Dae Whan Kim,
Dae Whan Kim
Korea Atomic Energy Research Institute, Daejeon, South Korea
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Dong Jin Kim,
Dong Jin Kim
Korea Atomic Energy Research Institute, Daejeon, South Korea
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Eoun Sun Kim,
Eoun Sun Kim
Korea Atomic Energy Research Institute, Daejeon, South Korea
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Hong Pyo Kim,
Hong Pyo Kim
Korea Atomic Energy Research Institute, Daejeon, South Korea
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Sung Ho Kim,
Sung Ho Kim
Korea Atomic Energy Research Institute, Daejeon, South Korea
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Weon-Ju Kim,
Weon-Ju Kim
Korea Atomic Energy Research Institute, Daejeon, South Korea
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Woo Gon Kim,
Woo Gon Kim
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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Young Do Kim
Young Do Kim
Hanyang University, Seoul, South Korea
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Ji Yeon Park
Korea Atomic Energy Research Institute, Daejeon, South Korea
Dae Whan Kim
Korea Atomic Energy Research Institute, Daejeon, South Korea
Dong Jin Kim
Korea Atomic Energy Research Institute, Daejeon, South Korea
Eoun Sun Kim
Korea Atomic Energy Research Institute, Daejeon, South Korea
Hong Pyo Kim
Korea Atomic Energy Research Institute, Daejeon, South Korea
Sung Ho Kim
Korea Atomic Energy Research Institute, Daejeon, South Korea
Weon-Ju Kim
Korea Atomic Energy Research Institute, Daejeon, South Korea
Woo Gon Kim
Korea Atomic Energy Research Institute, Daejeon, South Korea
Woo Seog Ryu
Korea Atomic Energy Research Institute, Daejeon, South Korea
Young Do Kim
Hanyang University, Seoul, South Korea
Paper No:
HTR2008-58149, pp. 43-47; 5 pages
Published Online:
July 1, 2009
Citation
Park, JY, Kim, DW, Kim, DJ, Kim, ES, Kim, HP, Kim, SH, Kim, W, Kim, WG, Ryu, WS, & Kim, YD. "Development of Materials for a High Temperature Gas Cooled Reactor in Korea." Proceedings of the Fourth International Topical Meeting on High Temperature Reactor Technology. Fourth International Topical Meeting on High Temperature Reactor Technology, Volume 2. Washington, DC, USA. September 28–October 1, 2008. pp. 43-47. ASME. https://doi.org/10.1115/HTR2008-58149
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