PLUTONIUM FUELS DEVELOPMENT
O.J. Wick, T.C. Nelson, Freshley
Abstract
O.J. Wick, T.C. Nelson, Freshley
Abstract
A description of plutonium fuel element development at Hanford including the fabrication of fuel for the Materials Test Reactor at Arco, Idaho, the fabrication of fuel for the Plutonium Recycle Test Reactor at Hanford, plutonium fabrication techniques under development, and irradiation testing of a variety of possible plutonium cortaining fuels is presented. The irradiation of alloys of aluminum containing up to 10 wt.% plutonium is described. These alloys have been irradiated to high burnouts and the results of these irradiations are presented. Plutonium containing fuel materials such as mixed crystal oxides of PuO/sub 2/ and UO/sub 2/ have been fabricated and irradiated. Fuel materials which consist of mixtures of inert materials which have been impregnated with PuO/sub 2/. The self-shielded fuel element concept is also being developed. (auth)
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A description of plutonium fuel element development at Hanford including the fabrication of fuel for the Materials Test Reactor at Arco, Idaho, the fabrication of fuel for the Plutonium Recycle Test Reactor at Hanford, plutonium fabrication techniques under development, and irradiation testing of a variety of possible plutonium cortaining fuels is presented. The irradiation of alloys of aluminum containing up to 10 wt.% plutonium is described. These alloys have been irradiated to high burnouts and the results of these irradiations are presented. Plutonium containing fuel materials such as mixed crystal oxides of PuO/sub 2/ and UO/sub 2/ have been fabricated and irradiated. Fuel materials which consist of mixtures of inert materials which have been impregnated with PuO/sub 2/. The self-shielded fuel element concept is also being developed. (auth)
Key concepts: Plutonium, Materials science, Fabrication, Inert, MOX fuel, Plutonium-240, Nuclear fuel, Irradiation