Highly localized azimuthal measurements in the CROCUS reactor towards the validaiton of high-fidelity neutronics codes

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In response to the need for validating high-fidelity deterministic neutronics solvers capable of pin-resolved neutron flux distributions, an instrumented fuel rod was designed for the experimental reactor CROCUS, operated by EPFL’s Laboratory for Reactor P ...

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We experimentally demonstrate the advantages of gamma detection for noise measurements to deter-mine the prompt neutron decay constant a of a nuclear reactor using the power spectral density (PSD) method, coupled to a new uncertainty estimation scheme base ...

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The Horizon2020 European project CORTEX aims at developing an innovative core monitoring technique that allows detecting anomalies in nuclear reactors, such as excessive vibrations of core internals, flow blockage, or coolant inlet perturbations. The techn ...

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Gamma rays in nuclear reactors, arising either from fission or decay processes, significantly contribute to the heating and dose of the reactor components. Zero power research reactors offer the possibility to measure gamma rays in a purely neutronic envir ...

The present article gives an overview of the first experimental campaigns carried out in the AKR-2 and CROCUS reactors within the framework of the Horizon 2020 European project CORTEX. CORTEX aims at developing innovative core monitoring techniques that al ...

The present article describes the preliminary validation study of simulated in-core and reflector n eutron spectra in preparation of oncoming experimental programs in the zero-power reactor CROCUS at EPFL. For this purpose, a set of activation foils were i ...

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The effects of neutron irradiation on austenitic stainless steels, usually used for the manufacturing of internal elements of nuclear reactors (e.g. the core shrouds), are the alteration of the microchemistry and the microstructure, and, as a consequence, ...

Highly localized azimuthal measurements in the CROCUS reactor towards the validaiton of high-fidelity neutronics codes

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Gamma-ray Spectroscopy in Low-Power Nuclear Research Reactors

Gamma noise to non-invasively monitor nuclear research reactors

Heterogeneous catalysis via light-heat dual activation: A path to the breakthrough in C1 chemistry

Design of an Instrumented Fuel Rod for Intra-pin Neutron Flux Measurements in the CROCUS Experimental Reactor

Metal Catalysts for the Electrochemical Reduction of CO2

Extension, validation, and optimization of Serpent/DYN3D/ATHLET code system for SFR applications

Advanced methodologies for modeling and assessment of SFR safety functions

High accuracy measurement of the prompt neutron decay constant in CROCUS using Gamma Noise and bootstrapped uncertainties

Development of a Novel Finite Volume Methodology for Multi-Dimensional Fuel Performance Applications

Delayed gamma fraction determination in the zero power reactor CROCUS

Analysis of the first COLIBRI fuel rods oscillation campaign in the CROCUS reactor for the European project CORTEX

Improved methodology for analysis and design of Molten Salt Reactors

A Coarse-mesh Methodology for the Analysis of One and Two-phase Nuclear Reactor Thermal-hydraulics in a Multi-physics Context

Design and Simulation of Gamma Spectrometry Experiments in the CROCUS Reactor

Neutron noise experiments in the AKR-2 and CROCUS reactors for the European project CORTEX

In-core dosimetry for the validation of neutron spectra in the CROCUS reactor

Compact string reactor for authotermal hydrogen production

Decomposition analysis of reactivity effect predictions for modern LWR fuel

Scale-down approach : chemical process optimisation using reaction calorimetry for the experimental simulation of industrial reactors dynamics

Effects of neutron irradiation on the microstructure and mechanical properties of the heat affected zone of stainless steel welds