共 50 条
- [41] THERMAL-HYDRAULIC ANALYSIS OF TEMPERATURE-FLUCTUATIONS - APPLICATION ON THE JETS ISSUING FROM THE FUEL ASSEMBLIES OF SUPERPHENIX ADVANCES IN NUCLEAR ENGINEERING COMPUTATION AND RADIATION SHIELDING, VOLS 1-2, 1989, : 606 - 609
- [42] DEVELOPMENT OF A THERMAL-HYDRAULIC ANALYSIS CODE FOR HELICAL COILED ONCE THROUGH STEAM GENERATOR PROCEEDINGS OF THE 26TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2018, VOL 6B, 2018,
- [44] WHOLE-CORE THERMAL-HYDRAULIC TRANSIENT CODE DEVELOPMENT AND VERIFICATION FOR LMFBR ANALYSIS TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1979, 32 (JUN): : 530 - 531
- [45] Thermal-hydraulic Code Development and Analysis of HTGR Helical Tube Supercritical Steam Generator Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2022, 56 (11): : 2343 - 2353
- [48] Research and development of real-time thermal-hydraulic simulation code for plate type fuel reactors Hedongli Gongcheng/Nuclear Power Engineering, 2010, 31 (06): : 56 - 63
- [50] DEVELOPMENT OF THERMAL-HYDRAULIC ANALYSIS MODELS FOR ATR JOURNAL OF THE ATOMIC ENERGY SOCIETY OF JAPAN, 1989, 31 (12): : 1343 - 1354