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EXAMINATION TECHNIQUES FOR HIGH BURNUP U--Pu FUEL ELEMENTS FOR FAST-BREEDER REACTORS.

B.J. Koprowski, F.L. Brown

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Key concepts: Burnup, Nuclear engineering, Breeder (animal), Fuel cycle, Breeder reactor, Environmental science, Uranium-233, MOX fuel

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EXAMINATION TECHNIQUES FOR HIGH BURNUP U--Pu FUEL ELEMENTS FOR FAST-BREEDER REACTORS. — Research Paper | ScholarLens