Title: High accuracy 234U(n,f) cross section in the resonance energy region
Authors: LEAL-CIDONCHA E.DURAN I.PARADELA DOBARRO CARLOSTASSAN-GOT L.AUDOUIN L.LEAL LUIZLE NAOUR C.NOGUERE G.TARRIO D.LEONG L. S.ALTSTADT S.ANDRZEJEWSKI J.BARBAGALLO M.BECARES V.BECVÁR F.BELLONI F.BERTHOUMIEUX E.BILLOWES J.BOCCONE V.BOSNAR D.BRUGGER M.CALVIANI M.CALVIÑO F.CANO-OTT D.CARRAPICO C.CERUTTI F.CHIAVERI E.CHIN M.COLONNA N.CORTES G.CORTES-GIRALDO M. A.DIAKAKI M.DOMINGO-PARDO C.DRESSLER R.ELEFTHERIADIS C.FERRARI A.FRAVAL K.GANESAN S.GARCIA A. R.GIUBRONE G.GOMEZ-HORNILLOS M. B.GONCALVES I.GONZALEZ-ROMERO E.GRIESMAYER E.GUERRERO C.GUNSING F.GURUSAMY P.HERNANDEZ-PRIETO A.JENKINS D. G.JERICHA E.KADI Y.KAEPPELER F.KARADIMOS D.KIVEL NIKOKOKKORIS M.KRTICKA M.KROLL J.LAMPOUDIS C.LANGER C.LEDERER C.LEEB H.LOSITO R.MALLICK A.MANOUSOS AMARGANIEC J.MARTÍNEZ T.MASSIMI C.MASTINU P.MASTROMARCO M.MEAZE M.MENDOZA E.MENGONI A.MILAZZO P. M.MINGRONE F.MIREA M.MONDELAERS WILLYPAVLIK ANDREASPERKOWSKI J.PLOMPEN ARJANPRAENA J.QUESADA J.RAUSCHER T.REIFARTH R.RIEGO A.ROBLES M. S.ROMAN F.RUBBIA C.SABATE-GILARTE MSARMENTO R.SAXENA A.SCHILLEBEECKX PETERSCHMIDT S.SCHUMANN D.TAGLIENTE G.TAIN J. L.TSINGANIS A.VALENTA S.VANNINI G.VARIALE V.VAZ P.VENTURA A.VERSACI R.VERMEULEN M.VLACHOUDIS V.VLASTOU R.WALLNER A.WARE T.WEIGAND M.WEISS C.WRIGHT T. J.ZUGEC P.
Citation: EPJ Web of Conferences vol. 146 p. 04057
Publisher: EDP Sciences
Publication Year: 2017
JRC N°: JRC108738
ISSN: 2100 014X
URI: http://publications.jrc.ec.europa.eu/repository/handle/JRC108738
DOI: 10.1051/epjconf/201714604057
Type: Articles in periodicals and books
Abstract: New results are presented of the 234U neutron-induced fission cross section, obtained with high accuracy in the resonance region by means of two methods using the 235U(n,f) as reference. The recent evaluation of the 235U(n,f) obtained with SAMMY by L. C. Leal et al. (these Proceedings), based on previous n_TOF data [1], has been used to calculate the 234U(n,f) cross section through the 234U/235U ratio, being here compared with the results obtained by using the n_TOF neutron flux.
JRC Directorate:Nuclear Safety and Security

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