SOME NEUTRON AND GAMMA RADIATION CHARACTERISTICS OF PLUTONIUM CERMET FUEL FOR ISOTOPIC POWER SOURCES.
Mound Lab., Miamisburg, Ohio), R Neff, M Anderson, Allen R. Campbell, F.X. Haas
Abstract
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Mound Lab., Miamisburg, Ohio), R Neff, M Anderson, Allen R. Campbell, F.X. Haas
Abstract
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Gamma and neutron measurements on various types of plutonium sources are presented in order to show the effects of O-17, O-18 F-19, Pu-236, age of the fuel, and size of the source on the gamma and neutron spectra. Analysis of the radiation measurements shows that fluorine is the main contributor to the neutron yields from present plutonium-molybdenum cermet fuel, while both fluorine and Pu-236 daughters contribute significantly to the gamma ray intensities.
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Gamma and neutron measurements on various types of plutonium sources are presented in order to show the effects of O-17, O-18 F-19, Pu-236, age of the fuel, and size of the source on the gamma and neutron spectra. Analysis of the radiation measurements shows that fluorine is the main contributor to the neutron yields from present plutonium-molybdenum cermet fuel, while both fluorine and Pu-236 daughters contribute significantly to the gamma ray intensities.
Key concepts: Oxide, Uranium oxide, Cermet, Radiochemistry, Neutron, Materials science, Metal, MOX fuel