共 50 条
- [42] Research on the Integrity of Lower Head of Reactor Pressure Vessel Based on Thermal-Mechanical Analysis Jixie Gongcheng Xuebao/Journal of Mechanical Engineering, 2025, 61 (02): : 141 - 150
- [43] REACTOR PRESSURE VESSEL INTEGRITY ASSESSMENT: FRENCH SIMPLIFIED ANALYSIS METHOD APPLIED TO UNDERCLAD POSTULATED DEFECT IN NOZZLE PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2016, VOL 7, 2017,
- [44] CREEP EVALUATION FOR A PWR REACTOR PRESSURE VESSEL LOWER HEAD UNDER SEVERE ACCIDENT CONDITIONS CONSIDERING SUSTAINED INTERNAL PRESSURE PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2018, VOL 3B, 2019,
- [45] Stress corrosion cracking in welds of reactor vessel nozzle at Ohi-3 and of other vessel's nozzle at Japan's PWR plants ASME Pressure Vessels Piping Div. Publ. PVP, (629-637):
- [46] Long-term Structural Integrity Analysis for Reactor Pressure Vessel under In-vessel Retention Condition Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2021, 55 (02): : 252 - 257
- [47] STRESS CORROSION CRACKING IN WELDS OF REACTOR VESSEL NOZZLE AT OHI-3 AND OF OTHER VESSEL'S NOZZLE AT JAPAN'S PWR PLANTS ASME PRESSURE VESSELS AND PIPING CONFERENCE 2009, VOL 1: CODES AND STANDARDS, 2010, : 629 - 637
- [48] APPLICATION OF NICKEL ELECTROPLATING FOR PWR REACTOR PRESSURE VESSEL CLADDING REPAIR PROCEEDINGS OF THE ASME 2020 PRESSURE VESSELS & PIPING CONFERENCE (PVP2020), VOL 1, 2020,
- [49] REACTOR PRESSURE VESSEL NOZZLE INNER-RADIUS EXAMINATION PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE - 2013, VOL 5, 2014,
- [50] Integrity assessment for aging reactor vessel of Japan's first generation PWR plants REACTOR DOSIMETRY: RADIATION METROLOGY AND ASSESSMENT, 2001, 1398 : 108 - 115