共 50 条
- [41] CALCULATION OF HYDRODYNAMICS OF PRIMARY COOLANT CIRCUIT IN NUCLEAR-POWER PLANTS EQUIPPED WITH WATER-COOLED WATER-MODERATED POWER-REACTORS FOR CASE OF LOSS OF COOLANT ACCIDENT KERNENERGIE, 1975, 18 (05): : 145 - 147
- [42] EFFICIENCY OF PRODUCING ADDITIONAL POWER IN UNITS OF NUCLEAR-POWER STATIONS CONTAINING WATER-COOLED WATER-MODERATED REACTORS SOVIET ATOMIC ENERGY, 1986, 61 (06): : 975 - 980
- [44] COMPUTER MODELING OF THE BEHAVIOR OF FLUE-ELEMENT CASINGS OF WATER-MODERATED WATER-COOLED POWER-REACTORS UNDER ACCIDENT CONDITIONS WITH AZIMUTHAL TEMPERATURE INHOMOGENEITIES SOVIET ATOMIC ENERGY, 1987, 63 (01): : 501 - 505
- [48] INCORPORATING RELIABILITY IN OPTIMIZING UNITS IN NUCLEAR-POWER STATIONS CONTAINING WATER-COOLED WATER-MODERATED REACTORS SOVIET ATOMIC ENERGY, 1984, 57 (03): : 593 - 599
- [49] Main ways of further improving safety on nuclear power stations with water-moderated water-cooled (VVER) reactors Thermal Engineering (English translation of Teploenergetika), 1989, 36 (12): : 657 - 661
- [50] Thermal and radiation characteristics of hydrazine in the primary loop of nuclear power plants with water-cooled, water-moderated reactors Atomic Energy, 1997, 82 : 92 - 98