참고문헌
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- v.B The Development of Expert System for Defect Identification and its Assessment Trans. of 9th SMiRT Conference Okamodo, A.;Kataoka, S.;Watanabe, M.
- 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.
- 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.
- Rules for Inspection and Testing of Components of Light Water Cooled Plants ASME Section XI
- Description of Stess-strain Curves by Three Parameters Ramberg, W.;Osgood, W. P.
- Electric Power Research Institute Techanical Report Ductile Fracture Handbook Zahoor, A.
- CEGB Report NO. R/H/R6 Assessment of the Integrity of Structures Containing Defects Harrison, R. P.;Loosemore, L.;Milne, I.
- Procedure for the Assessment of the Integrity of Nuclear Pressure Vessels and Piping Containing Defects Bloom, J. M.;Malik, S. N.
- 원전배관 건전성평가 기술 개발 이정배(외 11인)
- 영광원자력발전소 3 · 4호기용 2차계통 배관소재의 응력변형(σ-ε) 및 파괴저항(J-R)특성 김영진(외 12인)
- 대한기계학회논문집 v.19 no.4 원자력 배관재료의 파괴저항곡선 예측 장윤석;석창성;김영진
- 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.