Measurement of the neutron-induced fission cross-section of Am-243 relative to U-235 from 0.5 to 20 MeV
View/
Author
Belloni, F.
Calviani, M.
Colonna, N.
Mastinu, P.
Milazzo, P. M.
Abbondanno, U.
Aerts, G.
Alvarez, H.
Alvarez-Velarde, F.
Andriamonje, S.
Andrzejewski, J.
Audouin, L.
Badurek, G.
Barbagallo, M.
Baumann, P.
Becvar, F.
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.
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.
Kaeppeler, F.
Kadi, Y.
Karadimos, D.
Karamanis, D.
Kerveno, M.
Koehler, P.
Kossionides, E.
Krticka, M.
Lamboudis, C.
Leeb, H.
Lindote, A.
Lopes, I.
Lozano, M.
Lukic, S.
Marganiec, J.
Marrone, S.
Martinez, T.
Massimi, C.
Meaze, M. H.
Mengoni, A.
Moreau, C.
Mosconi, M.
Neves, F.
Oberhummer, H.
O'Brien, S.
Pancin, J.
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.
Attention
2299/10493
Abstract
The ratio of the neutron-induced fission cross-sections of Am-243 and U-235 was measured in the energy range from 0.5 to 20 MeV with uncertainties of approximate to 4%. The experiment was performed at the CERN n_TOF facility using a fast ionization chamber. With the good counting statistics that could be achieved thanks to the high instantaneous flux and the low backgrounds, the present results are useful for resolving discrepancies in previous data sets and are important for future reactors with improved fuel burn-up.