Transactions of the Korean Society of Mechanical Engineers A (대한기계학회논문집A)

The Korean Society of Mechanical Engineers (대한기계학회)
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Wear Properties of Nuclear Graphite IG-110 at Elevated Temperature

원자력용 흑연 IG-110 에 대한 고온 마모 특성 평가

  • Wei, Dunkun (Dept. of Mechanical Design Engineering, Chungnam Nat'l Univ.) ;
  • Kim, Jaehoon (Dept. of Mechanical Design Engineering, Chungnam Nat'l Univ.) ;
  • Kim, Yeonwook (Dept. of Mechanical Design Engineering, Chungnam Nat'l Univ.)
  • 위돈곤 (충남대학교 기계설계공학과 신뢰성평가실험실) ;
  • 김재훈 (충남대학교 기계설계공학과 신뢰성평가실험실) ;
  • 김연욱 (충남대학교 기계설계공학과 신뢰성평가실험실)
  • Received : 2013.03.29
  • Accepted : 2014.03.03
  • Published : 2014.05.01
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Abstract

The high temperature gas-cooled reactor (HTR-10) is designed to produce electricity and hydrogen. Graphite is used as reflector, support structures, and a moderator in reactor core; it has good resistance to neutron and is a suitable material at high temperatures. Friction is generated in the graphite structures for the core reflector, support structures, and moderator because of vibration from the HTR-10 fuel cycle flow. In this study, the wear characteristics of the isotropic graphite IG-110 used in HTR-10 were evaluated. The reciprocating wear test was carried out for graphite against graphite. The effects of changes in the contact load and sliding speeds at room temperature and $400^{\circ}C$ on the coefficient of friction and specific wear rate were evaluated. The wear behavior of graphite IG-110 was evaluated based on the wear surfaces.

고온가스로(HTR-10)는 전기 생산 및 수소 생산에 이용할 목적으로 설계되었다. 고온가스로의 노심에 반사체, 지지체, 감속재로 사용된 흑연은 중성자에 견디는 능력이 탁월하고, 고온 강도 및 열적특성이 우수하다. 구조물들은 연료 순환 유동 등으로 야기되는 진동 등에 의해 마찰이 발생하며 이는 구조물의 파괴를 초래한다. 따라서, 본 연구에서는 고온가스로에 사용되고 있는 등방성 흑연 IG-110에 대한 고온 마모 특성을 연구하였다. 왕복동 마모 시험을 수행하고 마모 특성의 결과로써 마찰계수와 비마모율을 도출하고 비교하였다. 시험 변수로써 실제 작동환경을 고려하여 상온과 고온 $400^{\circ}C$에서 미끄럼 속도와 접촉하중의 변화에 대한 결과를 도출하였다. 또한 흑연 IG-110의 마모 기구에 대해 토의하였다.

Keywords

References

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