Developments in data assimilation theory allow to adjust integral parameters and cross sections with stochastic sampling. This work investigates how two stochastic methods, MOCABA and BMC, perform relative to a sensitivity-based methodology called GLLS. Stochastic data assimilation can treat integral parameters that behave non-linearly with respect to nuclear data perturbations, which would be an advantage over GLLS. Additionally, BMC is compatible with integral parameters and nuclear data that have non-Gaussian distributions. In this work, MOCABA and BMC are compared to GLLS for a simple test case: JEZEBEL-Pu239 simulated with Serpent2. The three methods show good agreement between the mean values and uncertainties of their posterior calcu...
This paper describes the application of data assimilation methods to CASMO-5 simulations of a Proteu...
Nuclear data uncertainty propagation based on stochastic sampling ( SS) is becoming more attractive ...
Integral experiments in reactors or critical configurations claim to have very small experimental an...
Simulations of nuclear reactor physics can disagree significantly from experimental evidence, even w...
Current assimilation of integral experiments often consists in adjusting multi-group cross sections ...
Sensitivity coefficients from Monte Carlo neutron transport codes have uncertainties that can affect...
Data assimilation methods have recently been implemented in the sensitivity analysis and uncertainty...
International audienceIn this paper, we present three Monte Carlo methods to include integral benchm...
Nuclear data are widely used in many research fields. In particular, neutron-induced reaction cross ...
International audienceThe use of Data Assimilation methodologies, known also as a data adjustment, l...
Uncertainties in basic nuclear data and other quantities involved in the characterization of an expe...
Nuclear data used in designing of various nuclear applications (e.g., core design of reactors) is im...
Nuclear data used in designing of various nuclear applications (e.g., core design of reactors) is im...
This paper describes the application of data assimilation methods to CASMO-5 simulations of a Proteu...
Nuclear data uncertainty propagation based on stochastic sampling ( SS) is becoming more attractive ...
Integral experiments in reactors or critical configurations claim to have very small experimental an...
Simulations of nuclear reactor physics can disagree significantly from experimental evidence, even w...
Current assimilation of integral experiments often consists in adjusting multi-group cross sections ...
Sensitivity coefficients from Monte Carlo neutron transport codes have uncertainties that can affect...
Data assimilation methods have recently been implemented in the sensitivity analysis and uncertainty...
International audienceIn this paper, we present three Monte Carlo methods to include integral benchm...
Nuclear data are widely used in many research fields. In particular, neutron-induced reaction cross ...
International audienceThe use of Data Assimilation methodologies, known also as a data adjustment, l...
Uncertainties in basic nuclear data and other quantities involved in the characterization of an expe...
Nuclear data used in designing of various nuclear applications (e.g., core design of reactors) is im...
Nuclear data used in designing of various nuclear applications (e.g., core design of reactors) is im...
This paper describes the application of data assimilation methods to CASMO-5 simulations of a Proteu...
Nuclear data uncertainty propagation based on stochastic sampling ( SS) is becoming more attractive ...
Integral experiments in reactors or critical configurations claim to have very small experimental an...