New measurement of the 242Pu(n,γ) cross section at n-TOF-EAR1 for MOX fuels: Preliminary results in the RRR

J. Lerendegui-Marco, C. Guerrero, M. A. Cortés-Giraldo, J. M. Quesada, E. Mendoza, D. Cano-Ott, K. Eberhardt, A. Junghans, O. Aberle, J. Andrzejewski, L. Audouin, M. Bacak, J. Balibrea, M. Barbagallo, F. Bečvář, E. Berthoumieux, J. Billowes, D. Bosnar, A. Brown, M. CaamañoF. Calviño, M. Calviani, R. Cardella, A. Casanovas, F. Cerutti, Y. H. Chen, E. Chiaveri, N. Colonna, G. Cortés, L. Cosentino, L. A. Damone, M. Diakaki, C. Domingo-Pardo, R. Dressler, E. Dupont, I. Durán, B. Fernández-Domínguez, A. Ferrari, P. Ferreira, P. Finocchiaro, K. Göbel, M. B. Gómez-Hornillos, A. R. García, A. Gawlik, S. Gilardoni, T. Glodariu, I. F. Gonçalves, E. González, E. Griesmayer, F. Gunsing, H. Harada, S. Heinitz, J. Heyse, D. G. Jenkins, E. Jericha, F. Käppeler, Y. Kadi, A. Kalamara, P. Kavrigin, A. Kimura, N. Kivel, M. Kokkoris, M. Krtička, D. Kurtulgil, E. Leal-Cidoncha, C. Lederer, H. Leeb, S. Lo Meo, S. J. Lonsdale, D. Macina, J. Marganiec, T. Martínez, A. Masi, C. Massimi, P. Mastinu, M. Mastromarco, E. A. Maugeri, A. Mazzone, A. Mengoni, P. M. Milazzo, F. Mingrone, A. Musumarra, A. Negret, R. Nolte, A. Oprea, N. Patronis, A. Pavlik, J. Perkowski, I. Porras, J. Praena, D. Radeck, T. Rauscher, R. Reifarth, P. C. Rout, C. Rubbia, J. A. Ryan, M. Sabaté-Gilarte, A. Saxena, P. Schillebeeckx, D. Schumann, A. G. Smith, N. V. Sosnin, A. Stamatopoulos, G. Tagliente, J. L. Tain, A. Tarifeño-Saldivia, L. Tassan-Got, S. Valenta, G. Vannini, V. Variale, P. Vaz, A. Ventura, V. Vlachoudis, R. Vlastou, A. Wallner, S. Warren, P. J. Woods, T. Wright, P. Ž Ugec

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Abstract

The spent fuel of current nuclear reactors contains fissile plutonium isotopes that can be combined with 238U to make mixed oxide (MOX) fuel. In this way the Pu from spent fuel is used in a new reactor cycle, contributing to the long-term sustainability of nuclear energy. The use of MOX fuels in thermal and fast reactors requires accurate capture and fission cross sections. For the particular case of 242Pu, the previous neutron capture cross section measurements were made in the 70's, providing an uncertainty of about 35% in the keV region. In this context, the Nuclear Energy Agency recommends in its "High Priority Request List" and its report WPEC-26 that the capture cross section of 242Pu should be measured with an accuracy of at least 7-12% in the neutron energy range between 500 eV and 500 keV. This work presents a brief description of the measurement performed at n-TOF-EAR1, the data reduction process and the first ToF capture measurement on this isotope in the last 40 years, providing preliminary individual resonance parameters beyond the current energy limits in the evaluations, as well as a preliminary set of average resonance parameters.

Original languageEnglish
Title of host publicationND 2016
Subtitle of host publicationInternational Conference on Nuclear Data for Science and Technology
PublisherEDP Sciences
Volume146
ISBN (Electronic)9782759890200
DOIs
Publication statusPublished - 13 Sept 2017
Event2016 International Conference on Nuclear Data for Science and Technology, ND 2016 - Bruges, Belgium
Duration: 11 Sept 201616 Sept 2016

Conference

Conference2016 International Conference on Nuclear Data for Science and Technology, ND 2016
Country/TerritoryBelgium
CityBruges
Period11/09/1616/09/16

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