Measurement of the neutron-induced fission cross-section of 241Am at the time-of-flight facility n_TOF

F. Belloni, M. Calviani, N. Colonna, P. Mastinu, P. M. Milazzo, U. Abbondanno, G. Aerts, H. Álvarez, F. Alvarez-Velarde, S. Andriamonje, J. Andrzejewski, L. Audouin, G. Badurek, M. Barbagallo, P. Baumann, F. Běcvář, E. Berthoumieux, F. Calviño, D. Cano-Ott, R. CapoteC. Carrapiço, P. Cennini, V. Chepel, E. Chiaveri, G. Cortes, A. Couture, J. Cox, M. Dahlfors, S. David, I. Dillmann, C. Domingo-Pardo, W. Dridi, I. Duran, C. Eleftheriadis, M. Embid-Segura, A. Ferrari, R. Ferreira-Marques, K. Fujii, W. Furman, I. Goncalves, E. Gonzalez-Romero, A. Goverdovski, F. Gramegna, C. Guerrero, F. Gunsing, B. Haas, R. Haight, M. Heil, A. Herrera-Martinez, M. Igashira, E. Jericha, F. Käppeler, Y. Kadi, D. Karadimos, D. Karamanis, M. Kerveno, P. Koehler, E. Kossionides, M. Krtička, C. Lamboudis, H. Leeb, A. Lindote, I. Lopes, M. Lozano, S. Lukic, J. Marganiec, S. Marrone, T. Martínez, C. Massimi, M. H. Meaze, A. Mengoni, C. Moreau, M. Mosconi, F. Neves, H. Oberhummer, S. O'Brien, C. Papachristodoulou, C. Papadopoulos, C. Paradela, N. Patronis, A. Pavlik, P. Pavlopoulos, L. Perrot, M. T. Pigni, R. Plag, A. Plompen, A. Plukis, A. Poch, J. Praena, C. Pretel, J. Quesada, T. Rauscher, R. Reifarth, M. Rosetti, C. Rubbia, G. Rudolf, P. Rullhusen, J. Salgado, C. Santos, L. Sarchiapone, I. Savvidis, C. Stephan, G. Tagliente, J. L. Tain, D. Tarrio, L. Tassan-Got, L. Tavora, R. Terlizzi, G. Vannini, P. Vaz, A. Ventura, D. Villamarin, M. C. Vincente, V. Vlachoudis, R. Vlastou, F. Voss, S. Walter, M. Wiescher, K. Wisshak

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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 α- 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 ≈ 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.

Original languageEnglish
Article number2
Pages (from-to)1-6
Number of pages6
JournalEuropean Physical Journal A
Volume49
Issue number1
DOIs
StatePublished - 2013

Funding

FundersFunder number
Seventh Framework Programme249671
Seventh Framework Programme

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