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Fast reactor fission yields for /sup 233/U, /sup 235/U, /sup 238/U, /sup 239/Pu, and recommendations for the determination of burnup on FBR mixed oxide fuels

Conference · · Natl. Bur. Stand. (U.S.), Spec. Publ.; (United States)
OSTI ID:7348830
Absolute fast reactor fission yields are presented for over 40 stable and long-lived isotopes of Kr, Rb, Sr, Zr, Mo, Ru, Sb, Xe, Cs, Ba, La, Ce, Nd, and Sm for /sup 233/U, /sup 235/U, /sup 238/U, and /sup 239/Pu irradiated in EBR-II. A method for ordering fission yields as a function of neutron energy is given. Recommendations for the determination of burnup on mixed-oxide fuels irradiated in a fast reactor are given. (auth)
Research Organization:
Idaho Nuclear Engineering Lab., Idaho Falls
OSTI ID:
7348830
Conference Information:
Journal Name: Natl. Bur. Stand. (U.S.), Spec. Publ.; (United States) Journal Volume: 1:425
Country of Publication:
United States
Language:
English

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