共 50 条
- [11] Development of RCS-Containment Coupled Analysis Model and Evaluation of LBLOCA for APR-1400 26TH INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE (NENE 2017), 2017,
- [14] 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
- [15] Preliminary Study of the MCCI Phenomena on the APR1400 using MAAP 5.04 26TH INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE (NENE 2017), 2017,
- [18] DEVELOPMENT OF THE OPTIMIZED FATIGUE ANALYSIS PROCEDURE TO EVALUATE DESIGN LIFE FOR APR1400 ICONE16: PROCEEDING OF THE 16TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2008, VOL 1, 2008, : 665 - 670
- [20] SEISMIC ANALYSIS STUDY OF THE HP TURBINE STEAM SUPPLY PIPING FOR APR1400 PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE 2010, VOL 9, 2010, : 31 - 36