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Radiative neutron capture on Pu 242 in the resonance region at the CERN n-TOF-EAR1 facility
The spent fuel of current nuclear reactors contains fissile plutonium isotopes that can be combined with uranium to make mixed oxide (MOX) fuel. In this way the Pu from spent fuel is used in a new reactor cycle, contributing ...
Measurements of high-energy neutron-induced fission of (nat)Pb and (209)Bi
(EDP Sciences, 2010)
The CERN Neutron Time-Of-Flight (n_TOF) facility is well suited to measure low cross sections as those of neutron-induced fission in subactinides. The cross section ratios of (nat)Pb and (209)Bi relative to (235)U and ...