Journal of the Korean Physical Society

pISSN 0374-4884 eISSN 1976-8524
Qrcode

Article

J. Korean Phy. Soc. 2011; 59(2(3)): 1912-1915

Published online August 12, 2011     https://doi.org/10.3938/jkps.59.1912

Copyright © The Korean Physical Society.

Fission Cross-section Measurements of 233U, 245Cm and 241;243Am at CERN n_TOF Facility

M. Calviani, S. Andriamonje, E. Chiaveri, V. Vlachoudis, N. Colonna, M. H. Meaze, S. Marrone, G. Tagliente, R. Terlizzi, F. Belloni, U. Abbondanno, K. Fujii, P. M. Milazzo, C. Moreau, G. Aerts, E. Berthoumieux, W. Dridi, F. Gunsing, J. Pancin, L. Perrot, A. Plukis, H. Alvarez, I. Duran, C. Paradela, F. Alvarez-Velarde, D. Cano-Ott, E. Gonzalez-Romero, C. Guerrero, T. Martinez, D. Villamarin, M. C. Vicente, J. Andrzejewski, J. Marganiec, P. Assimakopoulos, D. Karadimos, D. Karamanis, C. Papachristodoulou, N. Patronis, L. Audouin, S. David, L. Ferrant, S. Isaev, C. Stephan, L. Tassan-Got, G. Badurek, E. Jericha, H. Leeb, H. Oberhummer, M. T. Pigni, P. Baumann, M. Kerveno, S. Lukic, G. Rudolf, F. Becvar, M. Krticka, F. Calvino, R. Capote, A. Carrillo De Albornoz

Abstract

Neutron-induced fission cross-sections of minor actinides have been measured using the n_TOF white neutron source at CERN, Geneva, as part of a large experimental program aiming at collecting new data relevant for nuclear astrophysics and for the design of advanced reactor systems. The measurements at n_TOF take advantage of the innovative features of the n_TOF facility, namely the wide energy range, high instantaneous neutron flux and good energy resolution. Final results on the fission cross-section of 233U, 245Cm and 243Am from thermal to 20 MeV are here reported, together with preliminary results for 241Am. The measurement have been performed with a dedicated Fast Ionization Chamber (FIC), a fission fragment detector with a very high efficiency, relative to the very well known cross-section of 235U, measured simultaneously with the same detector.

Keywords: neutron-induced fission reactions, Am, Cm, U, ND2010, Nuclear Data, ENDF, n_TOF