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Development and validation of calculation schemes dedicated to the interpreta...
Reactivity measurements by the oscillation technique, as those performed in the Minerve reactor, enable to access various neutronic parameters on materials, fuels or... -
Improvement of Sodium Neutronic Nuclear Data for the Computation of Generatio...
The safety criteria to be met for Generation IV sodium fast reactors (SFR) require reduced and mastered uncertainties on neutronic quantities of interest. Part of... -
Reactivity worth measurements on the CALIBAN reactor : interpretation of inte...
The good knowledge of nuclear data, input parameters for the neutron transport calculation codes, is necessary to support the advances of the nuclear industry. The... -
Fission fragment angular distribution and fission cross section validation
The present knowledge of angular distributions of neutron-induced fission is limited to a maximal energy of 15 MeV, with large discrepancies around 14 MeV. Only 238U... -
Gamma heating qualification in nuclear reactors
During the last few years, the g-heating issue has gained in stature, mainly for thesafety of the 3rd-generation reactors in which a stainless steel reflector is...
