共 50 条
- [32] PROBABILISTIC FRACTURE MECHANICS ANALYSIS FOR DEGRADED REACTOR PRESSURE VESSEL IN PRESSURIZED WATER REACTOR NUCLEAR POWER PLANT [J]. PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE - 2014, VOL 7, 2014,
- [33] Research and Improvement of Diagnosis Method of Fuel Failures for Pressurized Water Reactor Nuclear Power Plant [J]. Hedongli Gongcheng/Nuclear Power Engineering, 2019, 40 (03): : 43 - 47
- [34] EVALUATION TO DETERMINE FEASIBILITY OF REUSE OF REACTOR COOLANT IN A PRESSURIZED WATER NUCLEAR-POWER PLANT [J]. HEALTH PHYSICS, 1974, 27 (06): : 652 - 653
- [35] An Autocatalytic Model of a Pressurized Water Reactor in a Nuclear Power Generation [J]. SOFT COMPUTING IN DATA SCIENCE, SCDS 2015, 2015, 545 : 106 - 115
- [37] Simulation Study on Steam Dump Control System of Small Pressurized Water Reactor Nuclear Power Plant [J]. Hedongli Gongcheng/Nuclear Power Engineering, 2024, 45 (02): : 178 - 182
- [38] Hiberarchy of requirement analysis on diversity actuation system for advanced pressurized water reactor nuclear power plant [J]. Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2014, 48 : 950 - 954
- [40] INSTATIONARY PROCESSES IN A PRESSURIZED WATER NUCLEAR-POWER PLANT [J]. KERNENERGIE, 1987, 30 (11-12): : 449 - 454