A Sensitivity Study of a Steam Generator Tube Rupture for the SMART-P |
Kim Hee-Kyung
(Advanced Reactor Technology Development, Korea Atomic Energy Research Institute)
Chung Young-Jong (Advanced Reactor Technology Development, Korea Atomic Energy Research Institute) Yang Soo-Hyung (Advanced Reactor Technology Development, Korea Atomic Energy Research Institute) Kim Hee-Cheol (Advanced Reactor Technology Development, Korea Atomic Energy Research Institute) Zee Sung Quun (Advanced Reactor Technology Development, Korea Atomic Energy Research Institute) |
1 | 10CFR50, 'Domestic Licensing of Production and Utilization Facilities', Title 10, Code of Federal Regulations, Part 50, Appendix A, 'General Design Criteria for Nuclear Power Plant', April, 1993 |
2 | 윤한영 외, 'TASS/SMR 열수력 모델 기술서', KAERI/TR-1835/2001 |
3 | 10CFR100, 'Reactor Site Criteria', Part 100, April, 1962 |
4 | Young-Jong Chung et al., 'A Conservative Analysis Methodology for a Steamline Break Accident of the SMART-P Plant', Nuclear Technology, will be published |