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- [1] 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
- [3] Main steam line break accident simulation of APR1400 using the model of ATLAS facility INTERNATIONAL CONFERENCE ON NUCLEAR ENERGY TECHNOLOGIES AND SCIENCES (ICONETS 2017), 2018, 962
- [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):
- [9] 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,