共 50 条
- [1] THE POSSIBILITY OF MODELING RADIATION EMBRITTLEMENT OF THE STEELS USED FOR THE VESSELS OF WATER-MODERATED POWER-REACTORS SOVIET ATOMIC ENERGY, 1989, 66 (02): : 96 - 100
- [3] Studying helium accumulation in austenitic steels for evaluating radiation damage in internals of water-moderated water-cooled power reactors The Physics of Metals and Metallography, 2008, 106 : 503 - 509
- [4] Studying Helium Accumulation in Austenitic Steels for Evaluating Radiation Damage in Internals of Water-Moderated Water-Cooled Power Reactors PHYSICS OF METALS AND METALLOGRAPHY, 2008, 106 (05): : 503 - 509
- [5] TRITIUM CONTENT IN THE COOLANT OF WATER-COOLED-WATER-MODERATED REACTORS SOVIET ATOMIC ENERGY, 1979, 46 (02): : 85 - 89
- [6] PROSPECTS OF WATER-MODERATED WATER-COOLED POWER REACTORS SOVIET ATOMIC ENERGY-USSR, 1970, 28 (04): : 380 - &
- [7] SEMINAR ON WATER-COOLED WATER-MODERATED REACTORS IN FRANCE SOVIET ATOMIC ENERGY, 1976, 41 (02): : 778 - 779
- [8] WATER-LOSS TESTS IN WATER-COOLED AND -MODERATED RESEARCH REACTORS NUCLEAR SAFETY, 1967, 8 (06): : 590 - &
- [9] FUEL CYCLES FOR WATER-COOLED WATER-MODERATED THERMAL REACTORS SOVIET ATOMIC ENERGY-USSR, 1971, 30 (02): : 226 - &
- [10] SEMINAR ON THE THERMAL PHYSICS OF WATER-MODERATED - WATER-COOLED REACTORS SOVIET ATOMIC ENERGY, 1978, 45 (02): : 832 - 833