共 9 条
- [1] 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
- [2] Integrity assessment for aging reactor vessel of Japan's first generation PWR plants REACTOR DOSIMETRY: RADIATION METROLOGY AND ASSESSMENT, 2001, 1398 : 108 - 115
- [3] Stress intensity factors of corner cracks at set-in nozzle–cylinder intersection of a PWR reactor pressure vessel Journal of the Brazilian Society of Mechanical Sciences and Engineering, 2017, 39 : 601 - 611
- [5] 3-DIMENSIONAL FINITE ELEMENT T-STRESS CALCULATION FOR REACTOR PRESSURE VESSEL NOZZLE BLEND RADIUS SEMI-ELLIPTICAL SURFACE CRACKS ASME PRESSURE VESSELS AND PIPING CONFERENCE - 2015, VOL 2, 2015,
- [6] Estimation of threshold value for stress corrosion cracking of typical steel for pressure vessel under wet H2S environment MULTISCALE DAMAGE RELATED TO ENVIRONMENT ASSISTED CRACKING, 2005, : 37 - 42
- [7] Assessment of the reactor pressure vessel integrity in PTS conditions. Thermal hydraulic study of a safety injection in a three loop PWR plant with the finite element code N3S American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP, 2000, 414 : 137 - 140
- [8] Microstructure and Stress Corrosion Cracking of Dissimilar Metal Weld 16MND5/309L/308L/Z2CND18-12N Used for Connecting Reactor Pressure Vessel to Piping in Nuclear Power Plants PRESSURE VESSEL TECHNOLOGY: PREPARING FOR THE FUTURE, 2015, 130 : 1572 - 1579
- [9] Application of Modern Approaches to the Numerical Modeling of the Stress-Strain State for the Strength Assessment of Complex Units of the NPP Primary Circuit Equipment. Part 3. Application of Submodeling Technique and Extended Finite Element Method for Calculation of the Reactor Pressure Vessel Nozzle Zone STRENGTH OF MATERIALS, 2024, 56 (03) : 467 - 476