Publications associées à Appraisal of Core Analysis Methods against Zero-Power Experiments on Full-Scale BWR Fuel Assemblies

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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

Appraisal of Core Analysis Methods against Zero-Power Experiments on Full-Scale BWR Fuel Assemblies

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A mm(3) Fiber-Coupled Scintillator for In-Core Thermal Neutron Detection in CROCUS

Data assimilation of post irradiation examination experiments to adjust fission yields

Development and verification of a methodology for neutron noise response to fuel assembly vibrations

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

Data assimilation of post-irradiation examination data for fission yields from GEF

Loading optimization for Swiss used nuclear fuel assemblies into final disposal canisters

Experimental and numerical study of stochastic branching noise in nuclear reactors

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

Development and verification of pin-by-pin homogenized simplified transport solver Tortin for PWR core analysis

Synthesis of grid compliant substitute natural gas from a representative biogas mixture in a hybrid Ni/Ru catalysed reactor

Data assimilation of post-irradiation examination data for fission yields from GEF

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

Loading optimization for Swiss used nuclear fuel assemblies into final disposal canisters

Experimental and numerical study of stochastic branching noise in nuclear reactors

A mm(3) Fiber-Coupled Scintillator for In-Core Thermal Neutron Detection in CROCUS

Data assimilation of post irradiation examination experiments to adjust fission yields

Development and verification of a methodology for neutron noise response to fuel assembly vibrations

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

Development and verification of pin-by-pin homogenized simplified transport solver Tortin for PWR core analysis

Synthesis of grid compliant substitute natural gas from a representative biogas mixture in a hybrid Ni/Ru catalysed reactor