共 50 条
- [31] Investigation of plutonium in uranium products during spent fuel treatment PLUTONIUM FUTURES - THE SCIENCE, 2003, 673 : 45 - 46
- [32] 2 NODES MODEL FOR THERMAL TRANSIENTS OF CIRCULAR NUCLEAR FUEL-ELEMENTS ATOMKERNENERGIE, 1974, 23 (01): : 50 - 53
- [34] RECOVERY OF URANIUM FROM STAINLESS STEEL FUEL ELEMENTS INDUSTRIAL AND ENGINEERING CHEMISTRY, 1958, 50 (05): : 763 - 766
- [36] URANIUM-PLUTONIUM FUEL CYCLE FOR THERMAL AND FAST-REACTORS ENERGIA NUCLEARE, 1971, 18 (12): : 719 - &
- [37] FEATURES OF HEAT-TRANSFER DURING EMERGENCY COOLING OF FUEL-ELEMENTS KERNENERGIE, 1975, 18 (05): : 138 - 141
- [39] REVIEW OF STAINLESS-STEEL PROPERTIES FOR FAST-REACTOR FUEL-ELEMENTS JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1972, 11 (03): : 237 - &
- [40] METHODS OF FABRICATING URANIUM MONOCARBIDE, MONONITRIDE AND CARBONITRIDE CORES FOR FAST-REACTOR FUEL-ELEMENTS ATOMNAYA ENERGIYA, 1973, 35 (06): : 377 - 386