共 50 条
- [41] EMERGENCY COOLING SYSTEM FOR A NUCLEAR POWER GAS TURBINE ATOMKERNENERGIE, 1971, 18 (02): : 131 - &
- [43] Risk-Informing Nuclear Reactor Safety: The Prediction of the Probability of Core Damage Due to Loss of Power and Cooling ASCE-ASME JOURNAL OF RISK AND UNCERTAINTY IN ENGINEERING SYSTEMS PART B-MECHANICAL ENGINEERING, 2024, 10 (03):
- [44] APPLICABILITY OF EXISTING DATA FOR ANALYTICAL DESCRIPTION OF A NUCLEAR REACTOR ACCIDENT - EMERGENCY CORE-COOLING TEST PROGRAM SUPPORT NUCLEAR SAFETY, 1969, 10 (05): : 451 - &
- [45] APPLICABILITY OF EXISTING DATA FOR ANALYTICAL DESCRIPTION OF A NUCLEAR REACTOR ACCIDENT - EMERGENCY CORE-COOLING TEST PROGRAM SUPPORT NUCLEAR SAFETY, 1970, 11 (03): : 250 - &
- [46] APPLICABILITY OF EXISTING DATA FOR ANALYTICAL DESCRIPTION OF A NUCLEAR-REACTOR ACCIDENT - EMERGENCY CORE COOLING TEST PROGRAM SUPPORT NUCLEAR SAFETY, 1972, 13 (01): : 63 - &
- [47] METALLURGICAL EVALUATION OF SIMULATED BWR EMERGENCY CORE COOLING TESTS TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1971, 14 (01): : 141 - &
- [48] SEMISCALE BLOWDOWN AND EMERGENCY CORE COOLING (102 17 24) NUCLEAR SAFETY, 1972, 13 (05): : 412 - &
- [49] EMERGENCY CORE COOLING IN BABCOCK AND WILCOX PRESSURIZED WATER REACTORS TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1968, 11 (01): : 261 - &
- [50] SEMISCALE BLOWDOWN AND EMERGENCY CORE COOLING (102 17 24) NUCLEAR SAFETY, 1973, 14 (01): : 44 - 45