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Report No.

New measurement of the $$^{242}$$Pu(n, $$gamma$$) cross section at n_TOF-EAR1 for MOX fuels; Preliminary results in the RRR

Lerendegui-Marco, J.*; Guerrero, C.*; Harada, Hideo  ; Kimura, Atsushi; n_TOF Collaboration*; 115 of others*

The use of MOX fuels in thermal and fast reactors requires accurate capture and fission cross sections. For the particular case of $$^{242}$$Pu, the previous neutron capture cross section measurements were made in the 70's, providing an uncertainty of about 35% in the keV region. NEA WPEC-26 reports that the capture cross section of $$^{242}$$ Pu 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, as well as a preliminary set of average resonance parameters.



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