共 8 条
- [1] STOCHASTIC EVALUATION OF THE DYNAMIC RESPONSE AND THE CUMULATIVE DAMAGE OF NUCLEAR POWER PLANT PIPING. Memoirs of Faculty of Technology, Tokyo Metropolitan University, 1980, (30): : 2879 - 2896
- [2] Strength Analysis of Vertical Flow Steam Generators of Nuclear Power Plants. Mechanika Teoretyczna i Stosowana, 1981, 19 (02): : 217 - 224
- [3] Study on laser beam welding technology for nuclear power plants Nihon Kikai Gakkai Ronbunshu, B, 1600, 787 (445-449):
- [5] Using Sliding Live Steam Pressure to Control the Capacity of Power Units of Nuclear Power Plants. Teploenergetika, 1977, (01): : 39 - 42
- [6] ″ CONVOY ″ SATURATED STEAM TURBINE GENERATOR UNITS FOR NUCLEAR POWER PLANTS WITH PRESSURIZED WATER REACTORS. 1982, V 4 (N 4): : 183 - 186
- [7] Investigation of Corrosion Resistance of Materials for Steam Generator Tubes of Nuclear Power Plants with Water Cooled Reactors. Energomashinostroenie, 1980, (10): : 22 - 25
- [8] SEISMIC TEST RESULTS OF THE MAIN STEAM ISOLATION VALVE FOR JAPANESE BOILING WATER REACTOR NUCLEAR POWER PLANTS (PART 2) American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP, 2022, 5