TRIBUTYL PHOSPHATE SOLVENT EXTRACTION PROCESS FOR RECOVERY AND DECONTAMINATION OF URANIUM 235 FUEL DISCHARGED FROM EXPERIMENTAL BREEDER REACTOR TRIBUTYL PHOSPHATE SOLVENT EXTRACTION PROCESS FOR RECOVERY AND DECONTAMINATION OF URANIUM 235 FUEL DISCHARGED FROM EXPERIMENTAL BREEDER REACTOR
Data source
Japan Atomic Energy Agency's Library Catalog
A search system for the collections of the Japan Atomic Energy Agency central library. Books, reports, meeting materials, magazines and dockets collected by the library are searchable.
Last updated
July 18, 2022