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- [3] GAS PERMEABILITY OF GRAPHITE FUEL-ELEMENTS FOR HIGH-TEMPERATURE GAS-COOLED REACTOR AMERICAN CERAMIC SOCIETY BULLETIN, 1977, 56 (03): : 343 - 343
- [5] STUDIES ON THE THERMAL-CONDUCTIVITY OF THE GRAPHITE MATRIX OF HIGH-TEMPERATURE REACTOR-FUEL ELEMENTS ATOMKERNENERGIE-KERNTECHNIK, 1985, 47 (04): : 232 - 234
- [10] INVESTIGATIONS ON REPROCESSING OF GRAPHITE-CARBIDE FUEL FOR HIGH-TEMPERATURE REACTORS KERNTECHNIK ISOTOPENTECHNIK UND CHEMIE, 1966, 8 (03): : 110 - +