JURADO, B.; AICHE, M.; BARREAU, G.; BOYER, S.; CZAJKOWSKI, S.; DASSIÉ, D.; GROSJEAN, C.; GUIRAL, A.; HAAS, B.; OSMANOV, B.; PETIT, M.; BERTHOUMIEUX, E.; GUNSING, F.; PERROT, L.; THEISEN, C.; BAUGE, E.; MICHEL-SENDIS, F.; BILLEBAUD, A.; WILSON, J.N.; AHMAD, I.; GREENE, J.P.; JANSSENS, R.V.F.

doi:10.1063/1.2137222

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JURADO, B.
Centre d'Etudes Nucléaires de Bordeaux Gradignan [CENBG]

AICHE, M.
Centre d'Etudes Nucléaires de Bordeaux Gradignan [CENBG]

BARREAU, G.
Centre d'Etudes Nucléaires de Bordeaux Gradignan [CENBG]

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Nuclear fission and fission-product spectroscopy, Nuclear fission and fission-product spectroscopy, 2005-05-11, Chateau de Cadarache, Saint Paul Lez Durance. 2005, vol. 798, n° 798, p. 19-26

American Institute of Physics

Résumé en anglais

We present an original method that allows to determine neutron-induced cross sections of very short-lived minor actinides. This indirect method, based on the use of transfer reactions, has already been applied with success for the determination of the neutron-induced fission and capture cross section of 233Pa, a key nucleus in the 232Th-233U fuel cycle. A recent experiment using this technique has been performed to determine the neutron-induced fission cross sections of 242,243,244Cm and 241Am which are present in the nuclear waste of the current U-Pu fuel cycle. These cross sections are highly relevant for the design of reactors capable to incinerate minor actinides. The first results will be illustrated.< Réduire

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fission

neutron-nucleus reactions

curium

americium

nuclei with mass number 220 or higher

radioactive waste disposal

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Determination of minor actinides fission cross sections by means of transfer reactions

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