共 50 条
- [1] CODE FOR ANALYZING PARALLEL-CHANNEL THERMAL-HYDRAULICS IN EBR-II DURING NATURAL-CONVECTION CONDITIONS (CONVECT CODE) TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1975, 21 (JUN): : 299 - 300
- [2] DEVELOPMENT AND APPLICATION OF THE NEUTRONICS/THERMAL-HYDRAULICS COUPLING CODE FOR SAFETY ANALYSIS OF EBR-II LOSS OF HEAT SINK TESTS WITHOUT SCRAM PROCEEDINGS OF THE 24TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2016, VOL 4, 2016,
- [3] Operational reliability testing at EBR-II Nuclear Engineering International, 1981, 26 (318): : 42 - 44
- [5] THERMAL MIXING IN EBR-II OUTLET PLENUM TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1973, 16 (JUN): : 219 - 220
- [6] CYCLE TRANSIENT TESTING OF IRRADIATED EBR-II CLADDING TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1981, 38 (JUN): : 263 - 264
- [9] POWER CHANGE TESTING OF METALLIC EBR-II DRIVER FUEL TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1981, 38 (JUN): : 281 - 282
- [10] FRACTURE TESTING OF EBR-II STEAM-GENERATOR TUBING TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1981, 38 (JUN): : 321 - 322