The Molten Salt Reactor (MSR) is classified to be the only non-classical nuclear reactor type among the Generation IV reactors family. The reactor can be operated within the ~(232)Th -~(233)U fuel cycle as the thorium breeder. The precondition for breeding of new fissile material by MSR is the mastering of on-line reprocessing of liquid thorium-containing fuel of MSR. The main proposed reprocessing methods are pyrochemical fluoride technologies. The proposed flow-sheet of MSR on-line reprocessing is based on a combination of Molten-salt / liquid metal extraction and Electroseparation processes. In case of MSR thorium fuel reprocessing, the special attention must be paid to the separation of protactinium, uranium and thorium and to the proliferation resistance, which can be secured by denaturing of the isolated ~(233)U.
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