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- [6] DEVELOPMENT OF BONDING MATERIALS FOR HIGH TEMPERATURE GAS-COOLED REACTOR FUEL ELEMENTS AMERICAN CERAMIC SOCIETY BULLETIN, 1970, 49 (09): : 826 - &
- [7] GAS PERMEABILITY OF GRAPHITE FUEL-ELEMENTS FOR HIGH-TEMPERATURE GAS-COOLED REACTOR AMERICAN CERAMIC SOCIETY BULLETIN, 1977, 56 (03): : 343 - 343
- [9] SAFETY LIMITS ON FUEL FOR GAS-COOLED REACTORS AMERICAN CERAMIC SOCIETY BULLETIN, 1974, 53 (04): : 371 - 371