@misc{10481/52201,
year = {2017},
url = {http://hdl.handle.net/10481/52201},
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.},
organization = {This measurement has received funding from the EC FP7
Programme under the projects NEUTANDALUS (Grant
No. 334315) and CHANDA (Grant No. 605203), and the Spanish
Ministry of Economy and Competitiveness projects FPA2013-
45083-P and FPA2014-53290-C2-2-P.},
publisher = {EDP Sciences},
title = {New measurement of the 242Pu(n,γ ) cross section at n TOF-EAR1 for MOX fuels: Preliminary results in the RRR},
doi = {10.1051/epjconf/201714611045},
author = {Lerendegui-Marco, J. and TOF Collaboration and Porras Sánchez, José Ignacio and Praena Rodríguez, Antonio Javier},
}