This paper presents a Bayesian approach based on integral experiments to create correlations which do not appear with differential data. Some quantities such as the fission cross section (σ), neutron multiplicity (ν̅p), neutron spectra (χ), etc. are usually neither modeled together nor measured in coincidence, thus there is no correlation matrices in evaluated nuclear data libraries. One can nevertheless use the information from integral experiments such as fast criticality-safety benchmarks to correlate such quantities for possible inclusion in nuclear data libraries. A simple Bayesian set of equations is presented with random nuclear data, similarly to the usual methods applied with differential data. An example for 239Pu is proposed
Fission product yields are fundamental parameters for several nuclear engineering calculations and i...
Cross sections and fission yields can be correlated, depending on the selection of integral experime...
Nuclear data are widely used in many research fields. In particular, neutron-induced reaction cross ...
This paper presents a Bayesian approach based on integral experiments to create correlations which d...
International audienceThis paper presents a Bayesian approach based on integral experiments to creat...
International audienceThis paper presents a Bayesian approach based on integral experiments to creat...
Most recent evaluated nuclear data files exhibit excellent integral performance, as shown by the ver...
High-quality nuclear data is of prime importance while considering the design of advanced fast react...
International audienceThis paper presents an application of the Backward-Forward Monte Carlo (BFMC) ...
Integral experiments can be used to adjust ND-libraries and consequently the uncertainty response in...
International audienceIn this paper, we present three Monte Carlo methods to include integral benchm...
International audienceNuclear data, along with numerical methods and the associated calculation sche...
A Bayesian Monte Carlo method is outlined which allows a systematic evaluation of nuclear reactions ...
Abstract. The evaluation of neutron cross sections as a function of energy is fraught with inconsist...
We present an approach to uncertainty quantification for nuclear applica-tions, which combines the c...
Fission product yields are fundamental parameters for several nuclear engineering calculations and i...
Cross sections and fission yields can be correlated, depending on the selection of integral experime...
Nuclear data are widely used in many research fields. In particular, neutron-induced reaction cross ...
This paper presents a Bayesian approach based on integral experiments to create correlations which d...
International audienceThis paper presents a Bayesian approach based on integral experiments to creat...
International audienceThis paper presents a Bayesian approach based on integral experiments to creat...
Most recent evaluated nuclear data files exhibit excellent integral performance, as shown by the ver...
High-quality nuclear data is of prime importance while considering the design of advanced fast react...
International audienceThis paper presents an application of the Backward-Forward Monte Carlo (BFMC) ...
Integral experiments can be used to adjust ND-libraries and consequently the uncertainty response in...
International audienceIn this paper, we present three Monte Carlo methods to include integral benchm...
International audienceNuclear data, along with numerical methods and the associated calculation sche...
A Bayesian Monte Carlo method is outlined which allows a systematic evaluation of nuclear reactions ...
Abstract. The evaluation of neutron cross sections as a function of energy is fraught with inconsist...
We present an approach to uncertainty quantification for nuclear applica-tions, which combines the c...
Fission product yields are fundamental parameters for several nuclear engineering calculations and i...
Cross sections and fission yields can be correlated, depending on the selection of integral experime...
Nuclear data are widely used in many research fields. In particular, neutron-induced reaction cross ...