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公开(公告)号:US20220208401A1
公开(公告)日:2022-06-30
申请号:US17606001
申请日:2020-04-02
Applicant: KOREA ATOMIC ENERGY RESEARCH INSTITUTE
Inventor: Sang Chae JEON , Keon Sik KIM , Jong Hun KIM , Dong Joo KIM , Dong Seok KIM , Ji Hae YOON , Jae Ho YANG
IPC: G21C3/62 , C04B35/195 , C04B35/64
Abstract: The present invention relates to nuclear fuel pellets and a manufacturing method thereof, and more particularly, to nuclear fuel pellets comprising a trapping material of fission gas and a manufacturing method thereof. A nuclear fuel pellet of the present invention comprises a nuclear fuel; and a trapping material of fission gas, wherein the trapping material of the fission gas includes an oxide containing at least one element selected from the group consisting of silicon (Si), aluminum (Al) and barium (Ba) to exhibit an excellent trapping ability selective and independent for fission gas.
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2.
公开(公告)号:US20200283885A1
公开(公告)日:2020-09-10
申请号:US16762247
申请日:2018-11-14
Applicant: KOREA ATOMIC ENERGY RESEARCH INSTITUTE
Inventor: Jung Hwan PARK , Hyun Gil KIM , Yang II JUNG , Dong Jun PARK , Byoung Kwon CHOI , Young Ho LEE , Jae Ho YANG
Abstract: The present invention relates to a zirconium alloy cladding with improved oxidation resistance at a high temperature and a method of manufacturing the same. More particularly, the zirconium alloy cladding includes a zirconium alloy cladding; and a Cr—Al thin film coated on the cladding, wherein the thin film is deposited through arc ion plating and the content of Al in the thin film is 5% by weight to 20% by weight.
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