Publications associées à Systematic Sensitivity and Uncertainty Analysis of Sodium-Cooled Fast Reactor Systems

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Uncertainty and sensitivity analysis of PWR mini-core transients in the presence of nuclear data uncertainty using non-parametric tolerance limits

Andreas Pautz, Winfried Zwermann, Alexander Aures

The impact of nuclear data uncertainties is studied for the reactor power and the reactivity during control rod withdrawal transients with reactivity insertions of 0.5

and 0.97

, respectively, for a PWR mini-core model. Multi-group cross sections, the mul ...

PERGAMON-ELSEVIER SCIENCE LTD2020

Systematic Sensitivity and Uncertainty Analysis of Sodium-Cooled Fast Reactor Systems

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Uncertainty and sensitivity analysis of PWR mini-core transients in the presence of nuclear data uncertainty using non-parametric tolerance limits

Uncertainty propagation for the design study of the PETALE experimental programme in the CROCUS reactor

Treatment of the implicit effect in Shark-X

Uncertainty propagation based on correlated sampling technique for nuclear data applications

On data assimilation with Monte-Carlo-calculated and statistically uncertain sensitivity coefficients

Design Concept and Thermal & x2013;Mechanical Analysis of the Optical Mirror (M3) for the ITER ECH Upper Launcher

Reactor simulations with nuclear data uncertainties

Breed-and-burn fuel cycle in molten salt reactors

Application of multiphysics model order reduction to doppler/neutronic feedback

Determination of the activity inventory and associated uncertainty quantification for the CROCUS zero power research reactor

Reactor simulations with nuclear data uncertainties

Uncertainty and sensitivity analysis of PWR mini-core transients in the presence of nuclear data uncertainty using non-parametric tolerance limits

Uncertainty propagation for the design study of the PETALE experimental programme in the CROCUS reactor

Application of multiphysics model order reduction to doppler/neutronic feedback

Uncertainty propagation based on correlated sampling technique for nuclear data applications

Breed-and-burn fuel cycle in molten salt reactors

Determination of the activity inventory and associated uncertainty quantification for the CROCUS zero power research reactor

Design Concept and Thermal & x2013;Mechanical Analysis of the Optical Mirror (M3) for the ITER ECH Upper Launcher

Treatment of the implicit effect in Shark-X

On data assimilation with Monte-Carlo-calculated and statistically uncertain sensitivity coefficients