DOI QR코드

DOI QR Code

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

RCC-MR 코드에 기반한 ITER 시험증식블랑켓 일차벽 설계

  • Received : 2012.07.23
  • Accepted : 2012.11.16
  • Published : 2012.12.31

Abstract

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.

Keywords

allowable stress($S_m$);first wall(FW);nuclear fusion engineering;RCC-MR code;test blanket module(TBM);thermo-mechanical analysis;tresca stress

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