FIELD: manufacturing technology.
SUBSTANCE: invention relates to production of pelletized fuel for heat-generating elements of light-water reactors, in particular, WWER reactors. Higher thermal conductivity of uranium oxide fuel is ensured by polycrystalline particles of beryllium oxide uniformly distributed over volume of fuel pellet. Method of producing pellets of nuclear ceramic fuel with high heat conductivity involves introduction at the stage of preparation of press powder of powder of beryllium oxide, formation of homogeneous mixture with uranium dioxide and uranium oxide concentrate in amount of not more than 30 wt% of weight of press powder, preparation of press powder with dry binder and blowing agent, pellets pressing, their high-temperature sintering in reducing medium and dry grinding.
EFFECT: increased safety of uranium oxide fuel operation due to reduction of its temperature during irradiation from uranium dioxide production, as well as providing high nuclear purity of fuel pellets with high heat conductivity while maintaining neutron characteristics, density and grain size at the level of standard technology of pellets.
5 cl, 3 ex
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Authors
Dates
2020-02-05—Published
2016-12-29—Filed