1 |
Reed, J. W. and Kennedy, R. P., Methodology for Developing Seismic Fragilities, EPRI TR- 103959, Electric Power Research Institute, Palo Alto, California, 1994
|
2 |
Joe, Y. H., Cho, S. G., and Park, H. G., 'Comparative Study on Evaluation of Inelastic Energy Absorption Capacity for Seismic Fragility Analysis of Structures', Proc. of EESK Conference-Spring 2002, Earthquake Engineering Society of Korea, 2002, pp.135-142
|
3 |
USNRC, Design Response Spectra for Nuclear Power Plants, Regulatory Guide 1.60, Rev.1, U.S. Nuclear Regulatory Commission, 1973
|
4 |
KEPCO, Final Safety Analysis Report for Yonggwang Nuclear Units 3&4, Chapter 3.7, Korea Electric Power Corporation, 1993
|
5 |
USNRC, Individual Plant Examination of External Events(IPEEE) for Severe Accident Vulnerabilities, Generic Letter No.88-20, Supplement 4, US Nuclear Regulatory Commission, 1991
|
6 |
Newmark, N. M. and Hall, W. J., Development of Criteria for Seismic Review of Selected Nuclear Power Plants, USNRC Report NUREG/CR-0098, US Nuclear Regulatory Commission, 1978
|
7 |
USNRC, PRA Procedures Guide-A Guide to the Performance of Probabilistic Risk Assessments for Nuclear Power Plants, Final Report, Vol.I & Vol.II, NUREG/CR-2300, US Nuclear Regulatory Commission, 1982
|
8 |
Ravindra, M. K., 'Seismic Probabilistic Assessment and Its Impact on Margin Studies', J. of Nuclear Engineering and Design, Vol.107, 1988, pp.51-59
DOI
ScienceOn
|
9 |
Kennedy, R. P., et. al., 'Probabilistic Seismic Safety Study of an Existing Nuclear Power Plant', J. of Nuclear Engineering and Design, Vol.59, 1980, pp.315-338
DOI
ScienceOn
|
10 |
KAERI, Development of Integrated Nuclear Safety Assessment Technology (in Korean), KAERI/RR-1893/98, Korean Atomic Energy Research Institute, 1999
|
11 |
Park, B. Y., et al., 'Probabilistic Seismic Fragility Analysis for Nuclear Power Plants (in Korean)', Proc. of KSCE Conference (I), Korean Society of Civil Engineers, 1992, pp.125 -128
|
12 |
Joe, Y. H. and Cho, S. G., 'Seismic Fragility Analysis of Multi-Modes Structures Considering Modal Contribution Factor (in Korean)', J. of the Earthquake Engineering Society of Korea, Vol.6, No.4, 2002, pp.15-22
DOI
|
13 |
Ellingwood, B., 'Validation Studies of Seismic PRAs', J. of Nuclear Engineering and Design Vol.123, 1990, pp.189-196
DOI
ScienceOn
|
14 |
USNRC, Procedural and Submittal Guidance for the Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities, NUREG-1407, US Nuclear Regulatory Commission, 1991
|
15 |
Joe, Y. H., Park, H. G., and Cho, S. G., 'A State-of-the-Art of Probabilistic Seismic Fragility Analysis of Critical Structure', Proc. of EESK Conference-Spring 2000, Earthquake Engineering Society of Korea, 2000, pp.226-232
|
16 |
Huh, Jungwon, 'Nonlinear Structural Safety Assessment under Dynamic Excitation Using SFEM', J. of the Computational Structural Engineering Institute of Korea, Vol.13, No.3, 2000.9, pp.373-384
|
17 |
KEPCO, Individual Plant Examination of External Events For Yonggwang Nuclear Units 3&4, Final Report, Korea Electric Power Corporation, 1993
|
18 |
Ravindra, M. K., 'Seismic Individual Plant Examination of External Events of US Nuclear Power Plants: Insights and Implications', J. of Nuclear Engineering and Design, Vol.175, 1997, pp.227-236
DOI
ScienceOn
|
19 |
Kennedy R. P. and Ravindra, M. K., 'Seismic Fragilities for Nuclear Power Plant Risk Studies', J. of Nuclear Engineering and Design, Vol.79, No.1, 1984, pp.47-68
DOI
ScienceOn
|
20 |
Ebisawa, K. C., et. al., 'Evaluation of Response Factors for Seismic Probabilistic Safety Assessment of Nuclear Power Plants', J. of Nuclear Engineering and Design, Vol.147, 1994, pp.197-210
DOI
ScienceOn
|