Search Results - "Noguere, Gilles"

Generation of thermal scattering files with the CINEL code by Xu, Shuqi, Noguere, Gilles

“…The CINEL code dedicated to generate the thermal neutron scattering files in ENDF-6 format for solid crystalline, free gas materials and liquid water is…”
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Using effective temperature as a measure of the thermal scattering law uncertainties to UOX fuel calculations from room temperature to 80°C by Noguere, Gilles, Xu, Shuqi

“…The effective temperature T eff is an important physical quantity in neutronic calculations. It can be introduced in a Free Gas Model to approximate crystal…”
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Direct radiative capture calculations on 56Fe by Gkatis, Georgios, Diakaki, Maria, Mengoni, Alberto, Noguere, Gilles

“…The theoretical description of the 56Fe neutron induced reaction cross sections is the subject of many studies within the nuclear data community. Based on…”
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From nuclear physics to displacement damage calculation and uncertainty propagation in CONRAD by Chen, Shengli, Tamagno, Pierre, Bernard, David, Archier, Pascal, Noguere, Gilles

“…•Nuclear reaction models and radiation damage models are coupled to compute damage cross section.•Uncertainties of nuclear models and damage models are…”
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Time-of-flight measurements of MINERVE samples containing fission products and neutron absorbing isotopes by Noguere, Gilles, Geslot, Benoit, Gruel, Adrien, Kopecky, Stefan, Leconte, Pierre, Paradela, Carlos, Pottier, Mathilde, Schillebeeckx, Peter

“…The zero-power reactor MINERVE (CEA Cadarache) was designed to perform reactivity worth measurements by the oscillation technique. The various experimental…”
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CONRAD – a code for nuclear data modeling and evaluation by De Saint Jean, Cyrille, Tamagno, Pierre, Archier, Pascal, Noguere, Gilles

“…The CONRAD code is an object-oriented software tool developed at CEA since 2005. It aims at providing nuclear reaction model calculations, data assimilation…”
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Covariance generation for the prompt neutron multiplicity of 239Pu including the (n,γf) process by Leal-Cidoncha, Esther, Noguere, Gilles, Bouland, Olivier, Serot, Olivier

“…Fission cross section of 239Pu can be seen as a sum of the “immediate" fission and “two-step" (n,γf) reactions. In the Resolved Resonance Range of the reaction…”
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Towards the experimental validation of a small Time-Projection-Chamber for the quasi-absolute measurement of the fission cross section by Chatel, Carole, Mathieu, Ludovic, Aïche, Mourad, Diakaki, Maria, Noguere, Gilles, Bouland, Olivier

“…To accurately measure neutron-induced fission cross sections, to characterize neutron-beam lines or to make dosimetric investigations, it is necessary to have…”
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PROFIL-2 Experiment and neutron capture cross sections of Europium isotopes by Chen, Shengli, Noguere, Gilles, Bernard, David, De Saint Jean, Cyrille, Tommasi, Jean

“…Neutron-induced cross section is one of the key quantities in nuclear physics and nuclear engineering. The integral experiment can give good feedback to the…”
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On the use of Bayesian Monte-Carlo in evaluation of nuclear data by De Saint Jean, Cyrille, Archier, Pascal, Privas, Edwin, Noguere, Gilles

“…As model parameters, necessary ingredients of theoretical models, are not always predicted by theory, a formal mathematical framework associated to the…”
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Study of the (n,γf) process on 239Pu by Leal-Cidoncha, Esther, Noguere, Gilles, Bouland, Olivier, Serot, Olivier

“…In the neutron resonance range, fission cross section of 239Pu can be seen as a sum of the immediate (n,f) and the two-step (n,γf) fission reactions. In that…”
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Measurement of the double-differential neutron cross section of UO2 from room temperature to hot full power conditions by Noguere, Gilles, Xu, Shuqi, Filhol, Alain, Ollivier, Jacques, Farhi, Emmanuel, Calzavara, Yoan

“…Experimental phonon densities of states of UO2 have been deduced from double-differential neutron scattering data measured at 300 K, 600 K and 900 K using the…”
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Development and validation of uncertainty neutron transport calculations at an industrial scale by Gaillet, Julien, Bonaccorsi, Thomas, Noguere, Gilles, Truchet, Guillaume

“…Evaluating uncertainties on nuclear parameters such as reactivity is a major issue for conception of nuclear reactors. These uncertainties mainly come from the…”
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Experiments in the EXFOR library for evaluation of thermal neutron constants by Otuka, Naohiko, Capote, Roberto, Semkova, Valentina, Kawai, Takuma, Noguere, Gilles

“…E.J. Axton’s experimental database adopted in evaluation of thermal neutron constants by himself and also by a recent project to update the IAEA Neutron…”
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Feedback from experimental isotopic compositions of used nuclear fuels on neutron cross sections and cumulative fission yields of the JEFF-3.1.1 library by using integral data assimilation by Rizzo, Axel, Vaglio-Gaudard, Claire, Noguere, Gilles, Eschbach, Romain, Grassi, Gabriele, Martin, Julie-Fiona

“…Comparisons of calculated and experimental isotopic compositions of used nuclear fuels can provide valuable information on the quality of nuclear data involved…”
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Covariance Matrices for Differential and Angle-Integrated Neutron-Induced Elastic and Inelastic Scattering Cross Sections of 56Fe by Chen, Shengli, Bernard, David, Archier, Pascal, Cyrille De Saint Jean, Noguere, Gilles, Tamagno, Pierre

“…Correlations between neutron inelastic scatterings angular distributions are not included in the Joint Evaluated Fission and Fusion (JEFF) nuclear data…”
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Nuclear data adjustment based on the interpretation of post-irradiation experiments with the DARWIN2.3 package by Rizzo, Axel, Vaglio-Gaudard, Claire, Noguere, Gilles, Martin, Julie-Fiona, Vallet, Vanessa, Eschbach, Romain

“…DARWIN2.3 is the French reference package dedicated to fuel cycle applications, computing fuel inventory as well as decay heat, neutron emissions, α, β and γ…”
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New fit of thermal neutron constants (TNC) for 233,235U, 239,241Pu and 252Cf(sf): Microscopic vs. maxwellian data by Pronyaev, Vladimir G, Capote, Roberto, Trkov, Andrej, Noguere, Gilles, Wallner, Anton

“…An IAEA project to update the Neutron Standards is near completion. Traditionally, the Thermal Neutron Constants (TNC) evaluated data by Axton for…”
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On the use of the BMC to resolve Bayesian inference with nuisance parameters by Privas, Edwin, De Saint Jean, Cyrille, Noguere, Gilles

“…Nuclear data are widely used in many research fields. In particular, neutron-induced reaction cross sections play a major role in safety and criticality…”
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Impact of the thermal scattering law of H in H2O on the isothermal temperature reactivity coefficients for UOX and MOX fuel lattices in cold operating conditions by Juan Pablo Scotta, Noguere, Gilles, Bernard, David, Marquez Damian, Jose Ignacio, Santamarina, Alain

“…The contribution of the thermal scattering law of hydrogen in light water to isothermal temperature reactivity coefficients for UOX and MOX lattices was…”
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