EPJ Web of Conferences
Volume 111, 2016WONDER-2015 – 4th International Workshop On Nuclear Data Evaluation for Reactor applications
|Number of page(s)||7|
|Section||Microscopic Nuclear data Measurements|
|Published online||25 March 2016|
New measurement of the 242Pu(n,γ) cross section at n_TOF
1 Dpto. de Física Atómica, Molecular y Nuclear, Universidad de Sevilla, 41012 Sevilla, Spain
2 Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas (CIEMAT), 28040 Madrid, Spain
3 Johannes Gutenberg-Universität Mainz, 55128 Mainz, Germany
4 Helmholtz-Zentrum Dresden-Rossendorf, D-01314 Dresden, Germany
5 European Center for Nuclear Research (CERN), CH-1211 Geneva, Switzerland
a e-mail: firstname.lastname@example.org
Published online: 25 March 2016
The use of MOX fuel (mixed-oxide fuel made of UO2 and PuO2) in nuclear reactors allows substituting a large fraction of the enriched Uranium by Plutonium reprocessed from spent fuel. With the use of such new fuel composition rich in Pu, a better knowledge of the capture and fission cross sections of the Pu isotopes becomes very important. In particular, a new series of cross section evaluations have been recently carried out jointly by the European (JEFF) and United States (ENDF) nuclear data agencies. For the case of 242Pu, the two only neutron capture time-of-flight measurements available, from 1973 and 1976, are not consistent with each other, which calls for a new time-of flight capture cross section measurement. In order to contribute to a new evaluation, we have perfomed a neutron capture cross section measurement at the n_TOF-EAR1 facility at CERN using four C6D6 detectors, using a high purity target of 95 mg. The preliminary results assessing the quality and limitations (background, statistics and γ-flash effects) of this new experimental data are presented and discussed, taking into account that the aimed accuracy of the measurement ranges between 7% and 12% depending on the neutron energy region.
© Owned by the authors, published by EDP Sciences, 2016
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