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Uwaba, Tomoyuki; Yokoyama, Keisuke; Nemoto, Junichi*; Ishitani, Ikuo*; Ito, Masahiro*; Pelletier, M.*
Nuclear Engineering and Design, 359, p.110448_1 - 110448_7, 2020/04
Times Cited Count：2 Percentile：18.47(Nuclear Science & Technology)Coupled computer code analyses of irradiation performance of axially heterogeneous mixed oxide (MOX) fuel elements with high burnup in a fast reactor were conducted. Post-irradiation experiments revealed local concentration of Cs near the interfaces between MOX fuel and blanket columns including the internal blanket of the fuel elements as well as an increase in their cladding diameters. The analyses indicated that the local Cs concentration occurred as a result of Cs axial migration from the MOX fuels toward the blanket pellets near the interfaces. Swelling of the blanket pellets induced by the formation of low-density Cs-U-O compound was not sufficient to cause pellet-to-cladding mechanical interaction (PCMI). The PCMI analyzed in the MOX fuel column regions was insignificant, and the cladding diameter increases were caused mainly by void swelling in cladding and irradiation creep due to fission gas pressure.
Uwaba, Tomoyuki; Ito, Masahiro*; Ukai, Shigeharu; Pelletier, M.*
Journal of Nuclear Science and Technology, 42(7), p.608 - 617, 2005/07
Times Cited Count：9 Percentile：53.26(Nuclear Science & Technology)The bundle-duct interaction analysis code "BAMBOO" incorporated models of the fuel pin self bowing induced by thermal and void swelling strain difference in the circumferential direction and pin array disarrangement called dispersion into the deformation analysis. The code was verified by the use of post irradiation examinations of two high burn-up subassemblies in Phenix reactor.
Magnani, N.*; Caciuffo, R.*; Colineau, E.*; Wastin, F.*; Amoretti, G.*; Carretta, S.*; Santini, P.*; Baraldi, A.*; Capelletti, R.*; Adroja, D. T.*; et al.
no journal, ,
no abstracts in English
