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- [2] 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):
- [3] Preliminary Assessment of Mean Steam Line Break Accident in an Integral Pressurized Water Reactor(IPWR) 2011 ASIA-PACIFIC POWER AND ENERGY ENGINEERING CONFERENCE (APPEEC), 2011,
- [4] EXPERIMENTAL STUDY ON THE STEAM LINE BREAK (SLB) ACCIDENT WITH THE STEAM GENERATOR TUBE RUPTURE (SGTR) PROCEEDINGS OF THE 26TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2018, VOL 6A, 2018,
- [6] 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
- [9] AN EXPERIMENTAL STUDY OF STEAM GENERATOR TUBE LOADING DURING BLOWDOWN PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE - 2015, VOL 4, 2015,
- [10] SIMULATION OF SMALL STEAM GENERATOR TUBE BREAK (SSGTB) IN A SMALL PRESSURIZED WATER REACTOR (SPWR) PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 4, 2017,