共 50 条
- [31] New approach to the standardization of the characteristics of blowdown water for steam generators at VVER nuclear power plants Thermal Engineering (English translation of Teploenergetika), 1993, 40 (07):
- [32] SEISMIC TEST RESULTS OF THE MAIN STEAM ISOLATION VALVE FOR JAPANESE BOILING WATER REACTOR NUCLEAR POWER PLANTS PROCEEDINGS OF THE ASME 2020 PRESSURE VESSELS & PIPING CONFERENCE (PVP2020), VOL 9, 2020,
- [33] Characteristics of Operator Interface Management Tasks in Digital Main Control Room of Nuclear Power Plants Hedongli Gongcheng/Nuclear Power Engineering, 2019, 40 (04): : 91 - 95
- [35] Evaluation of Hydrogen Embrittlement Characteristics of Steels Used in Nuclear Power Plants. Kovove Materialy, 1979, CATV-4 (02): : 310 - 321
- [37] SEISMIC TEST RESULTS OF THE MAIN STEAM SAFETY RELIEF VALVE FOR JAPANESE BOILING WATER REACTOR NUCLEAR POWER PLANTS PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2017, VOL 8, 2017,
- [38] Investigation of Corrosion Resistance of Materials for Steam Generator Tubes of Nuclear Power Plants with Water Cooled Reactors. Energomashinostroenie, 1980, (10): : 22 - 25
- [39] Transient characteristics of main feedwater line rupture accident for AP1000 nuclear power plant Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2016, 50 (08): : 1422 - 1427
- [40] 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