CONVERSION OF SPENT URANIUM OXIDE FUEL INTO MOLTEN SALT REACTOR FUEL

    公开(公告)号:US20200027601A1

    公开(公告)日:2020-01-23

    申请号:US16085568

    申请日:2017-03-14

    申请人: Ian Richard SCOTT

    发明人: Ian Richard SCOTT

    摘要: There is described a method of reprocessing spent nuclear fuel. The spent nuclear fuel is added to an electro-reduction cell containing a halide salt electrolyte at a temperature above the melting point of the metallic form of uranium and higher actinides present in the spent nuclear fuel. The cell is operated so as to electrochemically reduce the spent nuclear fuel to form an alloy of uranium and higher actinides present in the spent nuclear fuel, wherein electrochemical reduction is continued until a concentration of unreduced components of the spent nuclear fuel is sufficiently low for the alloy to agglomerate.

    CONTROL OF CORROSION BY MOLTEN SALTS
    10.
    发明申请

    公开(公告)号:US20180286525A1

    公开(公告)日:2018-10-04

    申请号:US15764769

    申请日:2016-12-08

    申请人: Ian Richard SCOTT

    发明人: Ian Richard SCOTT

    摘要: A molten halide salt mixture for use in a nuclear fission reactor. The molten halide salt mixture comprises a reactive metal halide salt. The reactive metal halide salt is a halide salt of a reactive metal. The reactive metal has a Pauling electronegativity of at least 1.2, and at least one other halide salt of higher valence than the reactive metal halide salt. The reactive metal salt is at a concentration sufficient to prevent corrosion of metals in contact with the molten halide salt mixture and insufficient to cause deposition of the reactive metal at an operating temperature of the nuclear fission reactor.