共 50 条
- [21] FIBWR - A CODE FOR STEADY-STATE THERMAL-HYDRAULIC ANALYSIS OF BWR CORES TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1980, 35 (NOV): : 642 - 644
- [24] CORRELATION OF PWR STEAM-GENERATOR TUBE FAILURES WITH THERMAL-HYDRAULIC CHARACTERISTICS TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1975, 20 (APR21): : 192 - 195
- [25] THERMAL-HYDRAULIC CHARACTERISTICS OF A WESTINGHOUSE MODEL 51 STEAM GENERATOR - 1. Electric Power Research Institute (Report) EPRI NP, 1981, 1 (1721):
- [27] THERMAL-HYDRAULIC CHARACTERISTICS OF A WESTINGHOUSE MODEL F STEAM GENERATOR - 1. Electric Power Research Institute (Report) EPRI NP, 1981, 1 (1719):
- [30] Three-dimensional steady state thermal-hydraulic analysis of secondary side for CPR1000 steam generator Yuanzineng Kexue Jishu, 7 (1227-1231):