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Report No.
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FCA critical experiment for validation of $$^{235}$$U capture cross section and experimental analysis

Kugo, Teruhiko ; Kitamura, Yasunori; Fukushima, Masahiro   ; Ando, Masaki  ; Yamane, Tsuyoshi; Okajima, Shigeaki  

Sodium void reactivity experiments were performed at FCA using uranium fueled core to obtain integral data for evaluation of epithermal capture cross section of $$^{235}$$U. Experimental analysis were carried out with use of various nuclear data libraries including JENDL-4.0. The ratio of calculated value to experiment value (C/E) are less than unity with JENDL-3.3, ENDF/B-VII.0 and JEFF-3.1. This tendency of C/E values is similar to those for the sodium void reactivity experiments at BFS. Newly obtained integral data at FCA has a large sensitivity to $$^{235}$$U capture cross section from several hundreds eV to several keV. Thus, the new integral data are useful for validation of epithermal capture cross section of $$^{235}$$U and are used for the re-evaluation capture cross section of $$^{235}$$U in subgroup-29 of OECD/NEWA/NSC/WPEC.

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