共 50 条
- [41] FAST-REACTOR FISSION YIELDS FOR U-233 U-235 U-238 PU-239, AND RECOMMENDATIONS FOR DETERMINATION OF BURN-UP ON FBR MIXED-OXIDE FUELS BULLETIN OF THE AMERICAN PHYSICAL SOCIETY, 1975, 20 (02): : 151 - 151
- [43] DETERMINING PERCENTAGE COMPOSITION OF A MIXTURE OF U-235 AND PU-239 BY MEANS OF DELAYED NEUTRONS SOVIET ATOMIC ENERGY, 1975, 39 (06): : 1078 - 1081
- [45] APPLICATIONS OF NEUTRON-INDUCED AUTO-RADIOGRAPHY PU-239 AND U-235, U-238 IN TISSUES PROCEEDINGS OF THE AUSTRALIAN BIOCHEMICAL SOCIETY, 1979, 12 : 66 - 66
- [50] NEUTRON AND FISSION WIDTHS OF U-235, U-238, NP-237, PU-239, AM-241, AM-243 SOVIET JOURNAL OF NUCLEAR PHYSICS-USSR, 1986, 43 (02): : 185 - 187