Title: Measurement of the neutron-induced fission cross-section of 241Am at the time-of-flight facility n_TOF
Authors: BELLONI F.CALVIANI M.MEAZE M.MASTINU P.PRAENA J.MILAZZO P. M.AERTS G.ABBONDANNO U.ALVAREZ H.ALVAREZ-VELARDE F.ANDRIAMONJE S.ANDRZEJEWSKI J.AUDOUIN L.BADUREK G.BARBAGALLO M.BAUMANN P.Becvár F.BERTHOUMIEUX E.CALVIÑO F.CANO-OTT D.CAPOTE R.CARRAPIÇO C.CENNINI P.Chepel VCHIAVERI 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.FERRARI A.FERREIRA-MARQUES R.FUJII K.FURMAN W.GONÇALVES I.GONZALEZ-ROMERO E.GOVERDOVSKI A.GRAMEGNA F.GUERRERO C.GUNSING F.HAAS B.HAIGHT R.HEIL M.HERRERA-MARTINEZ A.IGASHIRA M.JERICHA E.KÄPPELER F.KADI Y.KARADIMOS D.KARAMANIS D.KERVENO M.KOEHLER P.KOSSIONIDES E.Krticka M.LAMPOUDIS CHRISTOSLEEB H.LINDOTE A.LOPES I.LOZANO M.LUKIC S.MARGANIEC J.MARRONE S.MARTÍNEZ T.MASSIMI C.MENGONI A.MOREAU C.MOSCONI M.NEVES F.OBERHUMMER H.O'BRIEN S.PAPACHRISTODOULOU C.PAPADOPOULOS C.PARADELA C.PATRONIS N.PAVLIK AndreasPAVLOPOULOS P.PERROT L.PIGNI M. T.PLAG R.PLOMPEN ArjanPLUKIS A.POCH A.PRETEL C.QUESADA J.RAUSCHER T.REIFARTH R.ROSETTI M.RUBBIA C.RUDOLF G.RULLHUSEN P.SALGADO J.SANTOS C.SARCHIAPONE L.SAVVIDIS I.STEPHAN C.TAGLIENTE G.TAIN J. L.TASSAN-GOT L.TAVORA L.TERLIZZI R.VANNINI G.VAZ P.VENTURA A.VILLAMARIN D.VINCENTE M. C.VLACHOUDIS V.VLASTOU R.VOSS F.WALTER S.WIESCHER M.WISSHAK K.TARRIO D.COLONNA N.
Citation: EUROPEAN PHYSICAL JOURNAL A vol. 49 no. 1 p. 2 [6 pages]
Publisher: SPRINGER
Publication Year: 2013
JRC N°: JRC77264
ISSN: 1434-6001
URI: http://link.springer.com/article/10.1140%2Fepja%2Fi2013-13002-3
http://publications.jrc.ec.europa.eu/repository/handle/JRC77264
DOI: 10.1140/epja/i2013-13002-3
Type: Articles in periodicals and books
Abstract: The neutron-induced fission cross section of 241Am has been measured relative to the standard fission cross section of 235U between 0.5 and 20 MeV. The experiment was performed at the CERN n_TOF facility. Fission fragments were detected by a fast ionization chamber by discriminating against the alpha-particles from the high radioactivity of the samples. The high instantaneous neutron flux and the low background of the n_TOF facility enabled us to obtain uncertainties of approximately 5%. With the present results it was possible to resolve discrepancies between previous data sets and to confirm current evaluations, thus providing important information for design studies of future reactors with improved fuel burn-up.
JRC Directorate:Health, Consumers and Reference Materials

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