학술논문

Measurement of the neutron-induced fission cross-section of 241Am at the time-of-flight facility n_TOF
Document Type
Original Paper
Author
Belloni, F.Calviani, M.Colonna, N.Mastinu, P.Milazzo, P. M.Abbondanno, U.Aerts, G.Álvarez, H.Alvarez-Velarde, F.Andriamonje, S.Andrzejewski, J.Audouin, L.Badurek, G.Barbagallo, M.Baumann, P.Bečvář, F.Berthoumieux, E.Calviño, F.Cano-Ott, D.Capote, R.Carrapiço, 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.Ferrari, A.Ferreira-Marques, R.Fujii, K.Furman, W.Goncalves, 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.Krtička, M.Lamboudis, C.Leeb, H.Lindote, A.Lopes, I.Lozano, M.Lukic, S.Marganiec, J.Marrone, S.Martínez, T.Massimi, C.Meaze, M. H.Mengoni, A.Moreau, C.Mosconi, M.Neves, F.Oberhummer, H.O’Brien, S.Papachristodoulou, C.Papadopoulos, C.Paradela, C.Patronis, N.Pavlik, A.Pavlopoulos, P.Perrot, L.Pigni, M. T.Plag, R.Plompen, A.Plukis, A.Poch, A.Praena, J.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.Tarrio, D.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.
Source
The European Physical Journal A: Hadrons and Nuclei. January 2013 49(1):1-6
Subject
Language
English
ISSN
1434-6001
1434-601X
Abstract
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 20MeV. The experiment was performed at the CERN n_TOF facility. Fission fragments were detected by a fast ionization chamber by discriminating against the $ \approx$ 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.