한국안전학회지 (Journal of the Korean Society of Safety)

  • 제27권6호
  • /
  • Pages.14-19
  • /
  • 2012
  • /
  • 1738-3803(pISSN)
  • /
  • 2383-9953(eISSN)
한국안전학회 (The Korean Society of Safety)
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RCC-MR 코드에 기반한 ITER 시험증식블랑켓 일차벽 설계

First Wall Design of ITER Test Blanket Module(TBM) based on RCC-MR Code

  • 신규인 (한국원자력연구원 핵융합공학기술개발센터) ;
  • 이동원 (한국원자력연구원 핵융합공학기술개발센터)
  • Shin, Kyu In (Nuclear Fusion Engineering Development Division, Korea Atomic Energy Research Institute) ;
  • Lee, Dong Won (Nuclear Fusion Engineering Development Division, Korea Atomic Energy Research Institute)
  • 투고 : 2012.07.23
  • 심사 : 2012.11.16
  • 발행 : 2012.12.31
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초록

The Helium cooled ceramic reflector(HCCR) test blanket module(TBM) has been designed and developed to participate the ITER(International Thermonuclear Experimental Reactor) test blanket program in Korea. The TBM was one of the main objectives for developing ITER for proving the tritium self-sufficiency and the heat transfers to produce the electricity with the breeding blanket concept. Among the TBM components, the first wall(FW) was the most important component in safety since it was directly faced a high level of a heat and fast neutrons from the plasma side and could protect the others components inside TBM. In this paper, the FW has been designed through the thermo-mechanical analysis considering ITER operation conditions. With the developed simple models, the stress limit analysis based on RCC-MR code which is the nuclear power plant design codes in France was evaluated for the allowable design criteria. The results showed that the designed FW model satisfied $1.5S_m$ or $3S_m$ of the allowable stress($S_m$) in RCC-MR code at the maximum stress region in the FW.

키워드

참고문헌

  1. IT-PD-440-11/00017, "한국형 고체형 TBM(H CSB) 개념 주도 전략(안),"국가핵융합연구소 보고서, 2011.
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