Record link: 
http://hdl.handle.net/20.500.12708/155136
-
Title: 
Measurement of the neutron-induced fission cross-section of ²⁴¹Am at the time-of-flight facility n_TOF
en
Citation: 
Belloni, F., Calviani, M., Colonna, N., Mastinu, P. F., 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., … Wisshak, K. (2013). Measurement of the neutron-induced fission cross-section of 241Am at the time-of-flight facility n_TOF. The European Physical Journal A, 49(1). https://doi.org/10.1140/epja/i2013-13002-3
-
Publisher DOI: 
10.1140/epja/i2013-13002-3
-
Publication Type: 
Article - Original Research Article
en
Language: 
English
-
Authors: 
Belloni, F. 
Calviani, Marco 
Colonna, N. 
Mastinu, P.F. 
Milazzo, P. M. 
Abbondanno, U. 
Aerts, G. 
Álvarez, H. 
Alvarez-Velarde, F. 
Andriamonje, S. 
Andrzejewski, J. 
Audouin, L. 
Badurek, Gerald 
Barbagallo, M. 
Baumann, P. 
Bečvář, F. 
Berthoumieux, E. 
Calviño, F. 
Cano-Ott, D. 
Jericha, Erwin 
Leeb, Helmut 
Oberhummer, Heinz 
Wisshak, K. 
-
Organisational Unit: 
E141-04 - Forschungsbereich Neutron- and Quantum Physics 
E141-03 - Forschungsbereich Nuclear and Particle Physics 
-
Journal: 
The European Physical Journal A 
-
ISSN: 
1434-6001
-
Date (published): 
Jan-2013
-
Number of Pages: 
6
-
Publisher: 
SPRINGER
-
Peer reviewed: 
Yes
-
Keywords: 
Nuclear and High Energy Physics; n_TOF facility; Neutron-induced fission; Advanced nuclear reactors; Minor actinides; Transmutation of nuclear waste
-
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 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.
en
Research Areas: 
Efficient Utilisation of Material Resources: 25%
Materials Characterization: 45%
Quantum Modelling and Simulation: 30%
-
Science Branch: 
Physik, Mechanik, Astronomie
-
Appears in Collections:
Article

Show full item record

Page view(s)

67
checked on Dec 1, 2023

Download(s)

2
checked on Dec 1, 2023

Google ScholarTM

Check