Irradiation testing of enhanced uranium oxide fuels

Annals of Nuclear Energy(2019)

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摘要
•Irradiation testing of uranium oxide fuel enhanced with Cr, SiO2/TiO2 and ThO2.•Irradiation testing of cladding coated with (Fe,Cr,Al) and (Cr,Al) alloys.•All tested materials perform as expected, or better.•Lowered fuel temperatures observed for fuel enhanced with Cr microcell structure.•Unexpectedly low temperatures observed for SiO2/TiO2 and 40% ThO2 enhanced fuel.
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关键词
Uranium oxide fuel,Additives,Thorium,Cladding coating,Halden reactor,Test irradiation
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