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        Neutron-induced fission cross section of Cm-245 : New results from data taken at the time-of-flight facility n_TOF

        Author
        Calviani, M.
        Meaze, M. H.
        Colonna, N.
        Praena, J.
        Abbondanno, U.
        Aerts, G.
        Alvarez, H.
        Alvarez-Velarde, F.
        Andriamonje, S.
        Andrzejewski, J.
        Assimakopoulos, P.
        Audouin, L.
        Badurek, G.
        Barbagallo, M.
        Baumann, P.
        Becvar, F.
        Belloni, F.
        Berthier, B.
        Berthoumieux, E.
        Calvino, F.
        Cano-Ott, D.
        Capote, R.
        Carrapico, C.
        Cennini, P.
        Chepel, V.
        Chiaveri, E.
        Cortes, G.
        Couture, A.
        Cox, J.
        Dahlfors, M.
        David, S.
        Dillmann, I.
        Domingo-Pardo, C.
        Dridi, W.
        Duran, I.
        Eleftheriadis, C.
        Embid-Segura, M.
        Ferrant, L.
        Ferrari, A.
        Ferreira-Marques, R.
        Fujii, K.
        Furman, W.
        Galanopoulos, S.
        Giubrone, G.
        Goncalves, I.
        Gonzalez-Romero, E.
        Goverdovski, A.
        Gramegna, F.
        Guerrero, C.
        Rauscher, T.
        N TOF Collaboration
        Attention
        2299/12238
        Abstract
        The neutron-induced fission cross section of Cm-245 was measured at n_TOF in a wide energy range and with high resolution. The energy dependence, measured in a single measurement from 30 meV to 1 MeV neutron energy, has been determined with 5% accuracy relative to the U-235(n,f) cross section. In order to reduce the uncertainty on the absolute value, the data have been normalized at thermal energy to recent measurements performed at ILL and BR1. In the energy range of overlap, the results are in fair agreement with some previous measurements and confirm, on average, the evaluated cross section in the ENDF/B-VII.0 database, although sizable differences are observed for some important resonances below 20 eV. A similar behavior is observed relative to JENDL/AC-2008, a reactor-oriented database for actinides. The new results contribute to the overall improvement of the databases needed for the design of advanced reactor systems and may lead to refinements of fission models for the actinides.
        Publication date
        2012-03-29
        Published in
        Physical Review C
        Published version
        https://doi.org/10.1103/PhysRevC.85.034616
        Other links
        http://hdl.handle.net/2299/12238
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