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- [7] STUDIES ON THE THERMAL-CONDUCTIVITY OF THE GRAPHITE MATRIX OF HIGH-TEMPERATURE REACTOR-FUEL ELEMENTS ATOMKERNENERGIE-KERNTECHNIK, 1985, 47 (04): : 232 - 234
- [8] DIFFUSION OF BARIUM IN SIMULATED HIGH-TEMPERATURE GRAPHITE FUEL ELEMENTS TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1964, 7 (02): : 451 - &
- [10] IRRADIATION RESULTS ON NATURAL URANIUM-GRAPHITE-GAS REACTOR-FUEL ELEMENTS BULLETIN D INFORMATIONS SCIENTIFIQUES ET TECHNIQUES DU COMMISSARIAT A L ENERGIE ATOMIQUE, 1974, (196): : 5 - 26