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

    Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

    1 Citation (Scopus)

    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
    EditorsPeter Siegler, Wim Mondelaers, Arjan Plompen, Franz-Josef Hambsch, Peter Schillebeeckx, Stefan Kopecky, Jan Heyse, Stephan Oberstedt
    PublisherEDP Sciences
    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

    Publication series

    NameEPJ Web of Conferences
    Volume146
    ISSN (Print)2101-6275
    ISSN (Electronic)2100-014X

    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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