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- [23] Recent approach of the secondary side corrosion modeling of alloy 600 for steam generator tubes ADVANCES IN MECHANICAL BEHAVIOUR, PLASTICITY AND DAMAGE, VOLS 1 AND 2, PROCEEDINGS, 2000, : 1181 - 1187
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- [26] AGING MANAGEMENT OF FRENCH PWR NUCLEAR STEAM GENERATORS USING STATISTICAL MODELING PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE - 2013, VOL 7: OPERATIONS, APPLICATIONS AND COMPONENTS, 2014,
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- [28] Simulation of Two-Phase Flow on the Secondary Side of PWR Steam Generator Tianjin Daxue Xuebao (Ziran Kexue yu Gongcheng Jishu Ban)/Journal of Tianjin University Science and Technology, 2019, 52 (07): : 745 - 753
- [29] Swelling of alloy 600 steam generators tubes and corrosion-fatigue in PWR primary water PROCEEDINGS OF THE EIGHTH INTERNATIONAL SYMPOSIUM ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, VOLS 1 AND 2, 1997, : 439 - 446