共 50 条
- [4] ONLINE MONITORING OF REACTOR INTERNALS FOR FLOW-INDUCED VIBRATION TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1974, 18 (JUN23): : 296 - 296
- [6] DEVELOPMENT OF STRUCTURAL INTEGRITY ASSESSMENT METHOD FOR FLOW-INDUCED VIBRATION OF REACTOR INTERNALS IN PWR PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2018, VOL 4, 2019,
- [7] Analysis of extreme value loads on flow-induced vibration testing for internals Hedongli Gongcheng/Nuclear Power Engineering, 1998, 19 (05): : 438 - 442
- [8] COMPRESSIBILITY AND ADDED MASSES IN THE BLOWDOWN ANALYSIS OF NUCLEAR-REACTOR INTERNALS ATOMKERNENERGIE-KERNTECHNIK, 1981, 39 (01): : 57 - 63
- [9] DEVELOPMENT OF AN ADVANCED PWR REACTOR INTERNALS SYSTEM FINITE ELEMENT MODEL FOR FLOW-INDUCED VIBRATION ANALYSES PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE - 2015, VOL 4, 2015,
- [10] Analysis method for flow-induced random load of reactors Liu, Tianyan (rexroi@hotmail.com), 1600, Atomic Energy Press (37): : 32 - 36