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

The Korean Society of Mechanical Engineers (대한기계학회)
권호 표지
DOI QR코드

DOI QR Code

Development of Nuclear Piping Integrity Expert System(I) - Evaluation Method RecomMendation and Material Properties Inference -

원자력배관 건전성평가 전문가시스템 개발(1) - 평가법 제시 및 재료물성치 추론 -

  • 김영진 (성균관대학교 기계설계학과) ;
  • 석창성 (성균관대학교 기계설계학과) ;
  • 최영환 (성균관대학교 대학원) ;
  • ;
  • Published : 1996.02.01
Download PDF
⟨ Previous Next ⟩

Abstract

The objective of this paper is to develop an expert system for nuclear piping integrity. This paper describes the selection methodology of integrity evalution method and the inference of material properties. To select the integrity evaluation method, the weight factor for respective material properties was obtained by the sensitivity analysis of the effect of material properties on integrity evaluation method. Subsequently the possession ratio for respective integrity evaluation method was computed, and the most appropriate integrity evaluation method for given input information is selected. In the material properties inference, stress-strain curves and J-R curves were predicted from tensile properties such as yield strength and tensile strength.

Keywords

References

  1. Lecture Notes in Engineering(Expert System in Structural Safety Assessment ESR Project : Expert System Aided Assessment Life of Pressured High Temperature Component Jovanovic, A.
  2. v.SD1 A Knowledge Based System for Structural Reliability Assessment Trans. of the SMiRT Conference Lucia, A. C.;Volta, G.
  3. v.B The Development of Expert System for Defect Identification and its Assessment Trans. of 9th SMiRT Conference Okamodo, A.;Kataoka, S.;Watanabe, M.
  4. Nuclear Engineering and Design 142 Development of Elastic-Plastic Integrity Evaluation System for Pressure Vessel and Piping Kim, Y. J.;Son, S. H.;Choi J. B.;Chung, H. D.
  5. KSME Journal v.8 no.2 Expert Systems Approach for Reactor Vessel Integrity Kim, Y. J.;Son, J. H.;Chung H. D.;Kim, J. G.
  6. Rules for Inspection and Testing of Components of Light Water Cooled Plants ASME Section XI
  7. Description of Stess-strain Curves by Three Parameters Ramberg, W.;Osgood, W. P.
  8. Electric Power Research Institute Techanical Report Ductile Fracture Handbook Zahoor, A.
  9. CEGB Report NO. R/H/R6 Assessment of the Integrity of Structures Containing Defects Harrison, R. P.;Loosemore, L.;Milne, I.
  10. Procedure for the Assessment of the Integrity of Nuclear Pressure Vessels and Piping Containing Defects Bloom, J. M.;Malik, S. N.
  11. 원전배관 건전성평가 기술 개발 이정배(외 11인)
  12. 영광원자력발전소 3 · 4호기용 2차계통 배관소재의 응력변형(σ-ε) 및 파괴저항(J-R)특성 김영진(외 12인)
  13. 대한기계학회논문집 v.19 no.4 원자력 배관재료의 파괴저항곡선 예측 장윤석;석창성;김영진
  14. Int. J. Pres. Ves. & Piping v.34 Leak Before Break : An Integrated Approach For High Energy Piping Chexal, V. K.;Norris, D. M.;Server, W. L.