共 50 条
- [41] MIXED-OXIDE FUEL PIN PERFORMANCE ANALYSIS USING OLYMPUS COMPUTER CODE TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1971, 14 (NAPR): : 6 - +
- [42] TRANSIENT OVERPOWER RESPONSE OF MIXED-OXIDE FUEL PINS TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1972, 15 (01): : 341 - &
- [43] NUCLEAR ASSAY TECHNIQUES FOR A MIXED-OXIDE FUEL PLANT TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1975, 22 (NOV16): : 143 - 143
- [44] PREDICTION OF PU-236 IN MIXED-OXIDE FUEL TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1976, 24 (NOV19): : 218 - 219
- [46] SAFETY ASPECTS OF A MIXED-OXIDE FUEL PRODUCTION PLANT TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1979, 31 (MAY): : 334 - 335
- [47] FINAL-STAGE DENSIFICATION OF MIXED-OXIDE FUEL AMERICAN CERAMIC SOCIETY BULLETIN, 1973, 52 (09): : 721 - 722
- [49] CREEP OF MIXED-OXIDE FUEL PELLETS AT HIGH STRESS AMERICAN CERAMIC SOCIETY BULLETIN, 1973, 52 (04): : 352 - 352
- [50] FINAL-STAGE DENSIFICATION OF MIXED-OXIDE FUEL AMERICAN CERAMIC SOCIETY BULLETIN, 1974, 53 (04): : 363 - 363