共 50 条
- [43] LOSS-OF-COOLANT ACCIDENT (LOCA) ANALYSIS - LOOP CODE DEVELOPMENT NUCLEAR SAFETY, 1974, 15 (01): : 92 - 92
- [45] WHOLE-CORE THERMAL-HYDRAULIC TRANSIENT CODE DEVELOPMENT AND VERIFICATION FOR LMFBR ANALYSIS TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1979, 32 (JUN): : 530 - 531
- [46] CLADDING MOTION MODEL FOR LMFBR LOSS-OF-FLOW ACCIDENT ANALYSIS TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1973, 17 (NOV): : 358 - 358
- [49] TREATMENT OF INCOHERENCIES AND UNCERTAINTIES IN LMFBR LOF ACCIDENT ANALYSIS WITH PARSEC. 1976, 3 : 1091 - 1100
- [50] A COMPREHENSIVE ANALYSIS OF FLOW-INDUCED ACCIDENT INITIATING CONDITIONS IN AN LMFBR TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1970, 13 (02): : 649 - &