Journal of Mechanical Science and Technology

  • 제17권7호
  • /
  • Pages.947-957
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  • 2003
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  • 1738-494X(pISSN)
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  • 1976-3824(eISSN)
대한기계학회 (The Korean Society of Mechanical Engineers)
권호 표지

Integrity Evaluation System of CANDU Reactor Pressure Tube

  • Kim, Young-Jin (Division of Mechanical Engineering, Sungkyunkwan University) ;
  • Kwak, Sang-Log (Safety System Research Team, Korea Railroad Research Institute) ;
  • Lee, Joon-Seong (Division of Mechanical System Design Engineering, Kyonggi University) ;
  • Park, Youn-Won (Division of Mechanics, Korea Institute of Nuclear Safety)
  • 발행 : 2003.07.01
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초록

The pressure tube is a major component of the CANDU reactor, which supports nuclear fuel bundle. In order to complete the integrity evaluation of pressure tube, expert knowledge, iterative calculation procedures and a lot of input data are required. More over, results of integrity assessment may be different according to the evaluation method. For this reason, an integrity evaluation system, which provides efficient way of evaluation with the help of attached database, was developed. The present system was built on the basis of 3D FEM results, ASME Sec. XI, and Fitness For Service Guidelines for CANDU pressure tubes issued by the AECL (Atomic Energy Canada Limited). The present system also covers the delayed hydride cracking and the blister evaluation, which are the characteristics of pressure tube integrity evaluation. In order to verify the present system, several case studies have been performed and the results were compared with those from AECL. A good agreement was observed between those two results.

키워드

참고문헌

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