共 50 条
- [31] Corrosion fatigue results for alloy 690 tubing in a PWR secondary side environment Proceedings of the ASME Pressure Vessels and Piping Conference - 2005, Vol 1, 2005, : 67 - 72
- [32] DEVELOPMENT OF DIGITAL TWINS OF PWR STEAM GENERATORS: DESCRIPTION OF TWO MAINTENANCE-ORIENTED USE CASES PROCEEDINGS OF 2021 28TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING (ICONE28), VOL 1, 2021,
- [33] Development and application of the SCC parameter to predicting SCC in the secondary side of steam generators PROCEEDINGS OF THE NINTH INTERNATIONAL SYMPOSIUM ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS-WATER REACTORS, 1999, : 689 - 694
- [34] Study of deposits and corrosion products in the secondary side of steam generators by Fourier Transform Infra Red Spectroscopy. Laboratory study PROCEEDINGS OF THE NINTH INTERNATIONAL SYMPOSIUM ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS-WATER REACTORS, 1999, : 577 - 586
- [36] THERMAL-HYDRAULIC RESPONSE OF THE SECONDARY SIDE OF A PWR STEAM GENERATOR WITH AN INTERNAL STRUCTURE TO A MAIN STEAM LINE BREAK PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE - 2015, VOL 4, 2015,
- [39] Stress corrosion cracking of alloy 600 and alloy 690 in hydrogen/steam and PWR primary side water PROCEEDINGS OF THE EIGHTH INTERNATIONAL SYMPOSIUM ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, VOLS 1 AND 2, 1997, : 274 - 281
- [40] Calculation model for 16N transit time in secondary side of steam generators Hedongli Gongcheng/Nuclear Power Engineering, 1998, 19 (02): : 106 - 110