Preliminary results on Am-241 transmutation in a high thermal flux

The possibility to transmute Am-241 by a high intensity thermal neutron flu x depends essentially on the value of the Am-242gs capture cross section. A s the recommended values given in the two most widely used nuclear data lib raries ENDF-B/VI and JEF-2.2 differ by more than a factor of 20, an experim ent has been carried out at the Institut Laue-Langevin in Grenoble (France) to fix this discrepancy. The obtained results and their impact on the pres ent understanding of nuclear waste incineration systems will be discussed.