Abstract: The present invention relates to antibody-drug conjugates (ADCs) wherein a plurality of active agents are conjugated to an antibody through at least one branched linker. The branched linker may comprise a branching unit, and two active agents are coupled to the branching unit through a secondary linker and the branching unit is coupled to the antibody by a primary linker. The active agents may be the same or different. In certain such embodiments, two or more such branched linkers are conjugated to the antibody, e.g., 2-4 branched linkers, which may each be coupled to a different C-terminal cysteine of a heavy or light chain of the antibody. The branched linker may comprise one active agent coupled to the branching unit by a first branch and a second branch that comprises a polyethylene glycol moiety coupled to the branching unit. In certain such embodiments, two or more such branched linkers are conjugated to the antibody, e.g.

Abstract: The present invention relates to a device for regenerating nerve cells and suppressing immune diseases, and more particularly, to a device for regenerating nerve cells and suppressing immune diseases, which uses a contact lens containing a conductive material to increase the effect of microcurrent on nerve cell regeneration and immune response suppression. The device for regenerating nerve cells and suppressing immune diseases comprises: a contact lens comprising a body configured to be worn on a cornea, and a conductive material inserted into the body and serving to induce a microcurrent generated outside the body; a plurality of channels configured to come into close contact with skins around eyes and to generate a flow of microcurrent on upper part of the contact lens; and a signal supply unit configured to supply electrical signals to the plurality of channels.

Abstract: Disclosed is a process for recovery of uranium from a spent nuclear fuel using a carbonate solution, characterized by excellent proliferation resistance of preventing leaching of transuranium element (TRU) nuclides such as Pu, Np, Am, Cm, etc. from the spent nuclear fuel as well as environmental friendliness of minimizing waste generation, wherein a highly alkaline carbonate solution is used to separate uranium alone from the spent nuclear fuel.

Abstract: Disclosed is a process for recovery of uranium from a spent nuclear fuel using a carbonate solution, characterized by excellent proliferation resistance of preventing leaching of transuranium element (TRU) nuclides such as Pu, Np, Am, Cm, etc. from the spent nuclear fuel as well as environmental friendliness of minimizing waste generation, wherein a highly alkaline carbonate solution is used to separate uranium alone from the spent nuclear fuel.