共 50 条
- [1] THE PROTOTYPE FAST-REACTOR, STEAM-GENERATORS - REPLY NUCLEAR ENERGY-JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1995, 34 (02): : 71 - 71
- [2] OPERATION OF PROTOTYPE FAST-REACTOR STEAM-GENERATORS LED DIRECTLY TO COMMERCIAL-SIZE DESIGN NUCLEAR ENGINEERING INTERNATIONAL, 1977, 22 (257): : 49 - 53
- [3] IAEA CONFERENCE ON LEAK DETECTION IN FAST-REACTOR STEAM-GENERATORS SOVIET ATOMIC ENERGY, 1979, 46 (01): : 72 - 73
- [4] FERRITIC STEELS FOR FAST-REACTOR STEAM-GENERATORS - CRITICAL-ASSESSMENT NUCLEAR ENERGY-JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1978, 17 (03): : 179 - 183
- [5] MAIN DEVELOPMENT DIRECTIONS OF THE SODIUM COOLED FAST-REACTOR STEAM-GENERATORS JADERNA ENERGIE, 1979, 25 (09): : 321 - 331
- [6] MEA SEMINAR ON EXPERIENCE GAINED WITH DESIGN AND DURING OPERATION OF FAST-REACTOR STEAM-GENERATORS KERNENERGIE, 1982, 25 (12): : 487 - 488
- [7] FRENCH FAST BREEDER REACTOR MAIN COMPONENTS - STEAM-GENERATORS TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1979, 31 (MAY): : 615 - 619
- [8] SOME ASPECTS OF THE BIG POWER MODULAR STEAM-GENERATORS DEVELOPMENT PROJECTION FOR THE FAST-REACTOR NUCLEAR-POWER STATIONS JADERNA ENERGIE, 1979, 25 (06): : 207 - 210
- [9] SELECTION OF VALUES OF DESIGN PEAK HEAT-FLUX TO REDUCE RISK OF WATERSIDE CORROSION IN FAST-REACTOR STEAM-GENERATORS JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1976, 15 (02): : 157 - 161
- [10] THE SAFETY OF THE PROTOTYPE FAST-REACTOR NUCLEAR ENERGY-JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1992, 31 (03): : 185 - 191