共 42 条
- [1] BEHAVIOR OF METALLIC-URANIUM TUBULAR FUEL ELEMENTS DURING HIGH-TEMPERATURE IRRADIATION [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1969, 12 (01): : 203 - &
- [2] ACHIEVING HIGH EXPOSURE IN METALLIC URANIUM FUEL ELEMENTS [J]. NUCLEAR APPLICATIONS AND TECHNOLOGY, 1970, 9 (05): : 673 - &
- [3] VALIDATION OF THE WIMS CODE FOR TUBULAR URANIUM FUEL-ELEMENTS [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1985, 49 (JUN): : 237 - 239
- [4] CHEMISTRY OF PROCESSING METALLIC URANIUM FUEL ELEMENTS WITH CHLORINE TRIFLUORIDE [J]. INDUSTRIAL AND ENGINEERING CHEMISTRY, 1959, 51 (02): : 179 - 184
- [5] MANUFACTURE OF SINTERED PASTILLES OF MIXED URANIUM AND THORIUM OXIDES WITH LOW URANIUM CONCENTRATIONS USING FUEL ELEMENTS [J]. METALLURGIA ITALIANA, 1971, 63 (04): : 134 - &
- [6] IRRADIATION BEHAVIOR OF ZIRCALOY-2-CLAD THORIUM-URANIUM ALLOY FUEL ELEMENTS [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1969, 12 (01): : 203 - &
- [7] RECOVERING URANIUM FROM GRAPHITE FUEL ELEMENTS [J]. INDUSTRIAL AND ENGINEERING CHEMISTRY, 1961, 53 (04): : 279 - 281
- [8] IRRADIATION OF METALLIC-URANIUM HOLLOWCORE FUEL ELEMENTS TO 1 AT PERCENT BURNUP [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1968, 11 (01): : 153 - &
- [9] IRRADIATION BEHAVIOR OF HOLLOW-CORE METALLIC-URANIUM FUEL ELEMENTS [J]. NUCLEAR APPLICATIONS, 1968, 4 (03): : 134 - &
- [10] URANIUM RECOVERY FROM UNIRRADIATED REACTOR FUEL ELEMENTS [J]. INDUSTRIAL & ENGINEERING CHEMISTRY PROCESS DESIGN AND DEVELOPMENT, 1963, 2 (02): : 127 - &