共 50 条
- [31] DISSOLUTION OF IRRADIATED MIXED-OXIDE FAST-REACTOR FUEL [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1972, 15 (01): : 86 - &
- [32] FUEL-CLAD REACTIONS IN IRRADIATED MIXED-OXIDE FUELS [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1971, 14 (NAPR): : 17 - &
- [33] NEW INSTRUMENTAL METHOD FOR DETERMINATION OF RETAINED FISSION-GAS [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1978, 28 (JUN): : 122 - 123
- [34] CALCULATION AND MEASUREMENT OF OXYGEN DISTRIBUTION IN IRRADIATED MIXED-OXIDE FUELS [J]. AMERICAN CERAMIC SOCIETY BULLETIN, 1972, 51 (04): : 393 - &
- [36] MICROSTRUCTURE OF MIXED-OXIDE FUEL IRRADIATED IN A THERMAL-NEUTRON FLUX [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1970, 13 (02): : 551 - &
- [38] TRITIUM ANALYSIS OF FAST FLUX IRRADIATED MIXED-OXIDE FUEL PINS [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1972, 15 (01): : 200 - &
- [39] DEMONSTRATION OF FISSION-GAS VENTING FROM FAST OXIDE REACTOR FUEL ELEMENTS [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1964, 7 (01): : 92 - &
- [40] THE USE OF THE ELECTRON-PROBE MICROANALYZER TO DETERMINE THE RADIAL-DISTRIBUTION OF FISSION-PRODUCTS IN IRRADIATED THERMAL REACTOR-FUEL [J]. JOURNAL DE PHYSIQUE, 1984, 45 (NC-2): : 829 - 832