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- [1] EFFECTS OF INITIAL PRESSURE AND LENGTH OF A BROKEN PIPE ON THE TRANSIENT HYDRAULIC LOADS ACTING ON NUCLEAR STEAM GENERATOR TUBES AND SUPPORTS DURING BLOWDOWN FOLLOWING A SUDDEN FEEDWATER PIPE BREAK PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2019, VOL 4, 2019,
- [2] PREDICTION OF TRANSIENT HYDRODYNAMIC LOADS ON THE PWR STEAM GENERATOR TUBES AT A MAIN FEED WATER LINE BREAK ACCIDENT PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2018, VOL 4, 2019,
- [3] THE STUDY OF THERMAL-HYDRAULIC ANALYSIS FOR FEEDWATER LINE BREAK IN STEAM GENERATOR PROCEEDINGS OF THE 20TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING AND THE ASME 2012 POWER CONFERENCE - 2012, VOL 1, 2012, : 603 - 609
- [7] Transient Hydraulic Response of a Pressurized Water Reactor Steam Generator to a Feedwater Line Break Using the Nonflashing Liquid Flow Model JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 2017, 139 (03):
- [8] VALIDATION OF A CFD ANALYSIS MODEL FOR THE THERMAL-HYDRAULIC RESPONSE OF PWR STEAM GENERATOR TO A STEAM LINE BREAK PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2016, VOL 4, 2017,
- [9] PWR CORE THERMAL-HYDRAULIC RESPONSE DURING STEAM LINE BREAK ACCIDENT TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1979, 32 (JUN): : 442 - 443
- [10] 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,