Development of expert system for nuclear piping integrity

Nuclear Engineering and Design

Volumn 174, Issue 1, 1997, Pages 69-78

  Kim, Y J ^a   Suh, M W ^a   Jun, H K ^a   Park, Y W ^b   Choi, Y H ^b  

^a Sungkyunkwan University   (South Korea)

^b Korea Institute of Nuclear Safety (KINS)   (South Korea)

Author keywords

[No Author keywords available]

Indexed keywords

EID: 0003162839     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(97)00070-8     Document Type: Article

References (11)

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2. Jovanovic, A., Maile, K., 1993. Review of MPA research projects in the field of knowledge-based systems for power plant application, Trans. 12th SMiRT Conf., Vol. SD102/ 3, pp. 195-200.
3. Lucia, A.C., Barbaro, P., 1993. Knowledge engineering application for the management of ageing plants, Trans. 12th SMiRT Conf., Vol. SD101/3, pp. 171-176.
4. Kim, Y.J., Choy, Y.S., Seok, C.S., Yang, K.M., Ra, I.S., Ahn, H.Y., 1993. Fracture properties evaluation of BOP piping system for the Yonggwang 3 and 4 nuclear generating station, Trans. 12th SMiRT Conf., Vol. G, pp. 435-440.
5. Chexal, V.K., Norris, D.M., Server, W.L., 1988. Leak-Before-Break: An integrated approach for high energy pip-ing. Int. J. Pressure Vessel Piping 34, 237-254.
6. ASME, 1992. ASME Boiler and pressure vessel code, ASME Task Group.
7. Kim, Y.J., Seok, C.S., Chang, Y.S., 1996. Prediction of fracture resistance curve from tensile data for carbon steel piping material. Int. J. Pressure Vessel Piping 68, 209-217.
8. Bloom, J.M., Malik, S.N., 1982. Procedure for the assessment of the integrity of nuclear pressure vessels and piping containing defects, EPRI NP-2431.
9. Norris, D.M., 1988. Evaluation of flaws in ferritic piping, EPRI NP-6045, 3.4-3.5.
10. Kussmaul, K., Roos, E., 1985. Statistical evaluation of post-yield fracture mechanics properties on the base of the notched bar impact test. Nucl. Eng. Des. 87, 123-137.
11. Zahoor, A., 1989. Ductile Fracture Handbook, Vol. I-III, EPRI NP 6301-D, N14-1.