共 50 条
- [1] THE FAST-NEUTRON REACTOR-FUEL ELEMENT AND ITS BEHAVIOR ANNALES DE CHIMIE-SCIENCE DES MATERIAUX, 1984, 9 (04): : 423 - 431
- [2] NEUTRON DOSIMETRY CHARACTERIZATION OF SPENT THERMAL REACTOR-FUEL ASSEMBLIES TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1979, 32 (JUN): : 634 - 635
- [4] QUALITY ANALYSIS IN PRESSURIZED WATER REACTOR-FUEL TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1975, 20 (APR21): : 572 - 574
- [7] COMPARISON OF CERTAIN METHODS OF CALCULATING NEUTRON FLUXES IN A REACTOR-FUEL CHANNEL SOVIET ATOMIC ENERGY, 1980, 48 (03): : 165 - 168
- [9] POSTIRRADIATION EXAMINATION OF REACTOR-FUEL AMERICAN CERAMIC SOCIETY BULLETIN, 1974, 53 (04): : 368 - 368