Journal of the Korean Ceramic Society (한국세라믹학회지)

The Korean Ceramic Society (한국세라믹학회)
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Fracture Properties of Nuclear Graphite Grade IG-110

원자로용급 흑연인 IG-110의 파괴특성

  • Han, Dong-Yun (Department of Materials Science and Engineering, Myongji University) ;
  • Kim, Eung-Sun (Korea Atomic Energy Research Institute, Nuclear Hydrogen Project Team) ;
  • Chi, Se-Hwan (Korea Atomic Energy Research Institute, Nuclear Hydrogen Project Team) ;
  • Lim, Yun-Soo (Department of Materials Science and Engineering, Myongji University)
  • 한동윤 (명지대학교 신소재공학과) ;
  • 김응선 (한국원자력연구소 원자력수소사업추진단) ;
  • 지세환 (한국원자력연구소 원자력수소사업추진단) ;
  • 임연수 (명지대학교 신소재공학과)
  • Published : 2006.07.01
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Abstract

Artificial graphite generally manufactured by carbonization sintering of shape-body of kneaded mixture using granular cokes as filler and pitch as binder, going through pitch impregnation process if necessary and finally applying graphitization heat treatment. Graphite materials are used for core internal structural components of the High-Temperature Gas-cooled Reactors (HTGR) because of their excellent heat resistibility and resistance of crack progress. The HTGR has a core consisting of an array of stacked graphite fuel blocks are machined from IG-110, a high-strength, fine-grained isotropic graphite. In this study, crack stabilization and micro-structures were measured by bend strength and fracture toughness of isotropic graphite grade IG-110. It is important to the reactor designer as they may govern the life of the graphite components and hence the life of the reactor. It was resulted crack propagation, bend strength, compressive strength and micro-structures of IG-110 graphite by scanning electron microscope and universal test machine.

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References

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