MANUFACTURE OF NUCLEAR FUEL FOR FAST BREEDER REACTOR AND NUCLEAR FUEL FOR FAST BREEDER MANUFACTURED BY THE METHOD AS WELL AS PLAN SUITABLE FOR REALIZATION OF THE METHOD

摘要

PROBLEM TO BE SOLVED: To simplify a reprocessing process, to enhance the economical efficiency of the process, to reduce the waste fluid of a processing facility and to simplify the processing facility by a method wherein a condition under which a plutonium/uranium ratio which can be used as a nuclear fuel for a reactor core can be extracted reversely to a waste phase is set in advance and a reverse extraction is performed. SOLUTION: Three types are available as reprocessing methods of a nuclear fuel. A batch processing system A is a system wherein both nuclear fuels for a blanket and a reactor core are dissolved in nitric acid so as to be extracted and processed. A second system is a general processing system B, and it is a system wherein both nuclear fuels are dissolved by nitric acid, a crystallization treatment is executed, excess uranium is removed in advance as a crystallization salt and a crystallization mother liquid is mixed so as to be transferred to a reverse extraction treatment. A third system is a separated treatment system C, and it is a system wherein the fuel for the reactor core is processed by the system A and the fuel for the blanket is processed by the system B so as to be processed separately according to the kind of a fuel. In the system B, the crystallization salt is separated after the crystallization treatment so as to be changed into a raw material for the blanket via a kiln-type dewatering and denitration process and a blanket granule roasting-reduction process. In this manner, a reprocessing process can be simplified down to 20 to 25%, a waste fluid is reduced, and a processing facility can be simplified.