Grégory Perret
YOU?
Author Swipe
Pressurized Thermal Shock Analysis with Uncertainty Propagation for the APAL Project Using TRACE and FAVOR Open
Pressurized thermal shock following a loss-of-coolant accidental scenario has been recognized as a safety concern for the integrity of the reactor pressure vessel since the 1980s. In the context of the recent APAL (Advanced PTS Analysis fo…
Choked-flow model parameter uncertainty determination using hierarchical calibration Open
Nowadays Best Estimate Plus Uncertainty (BEPU) methods are applied in nuclear safety investigations with thermal-hydraulics system codes. Their applications remain challenging because (1) many semi-empirical parameterized models are releva…
The influence of droplet breakup model on the prediction of reactor core parameters during reflood conditions Open
During reflood conditions, spacer grids affect the complex flow dynamics inside the reactor core. They can breakup the dispersed droplets, thereby significantly reducing their diameters. This process enhances local heat and mass interfacia…
Non-destructive analysis of spent fuel samples using a gamma-blind fast neutron detector Open
This paper presents the capabilities of a measurement setup built to measure the axial distribution of neutron emitters in spent fuel pins from nuclear power plants. The measurement system uses a custom gamma-blind detector based on a nove…
Global Sensitivity Analysis and Bayesian Calibration on a Series of Reflood Experiments with Varying Boundary Conditions Open
Best estimate plus uncertainty for the safety assessment of nuclear power plant transient requires, among others, estimating the probability density function (PDF) of physical model parameters in thermal-hydraulic system codes. In that con…
NEUTRON EMISSION MEASUREMENTS OF PWR SPENT FUEL SEGMENTS AND PRELIMINARY VALIDATION OF DEPLETION CALCULATIONS Open
Assessing neutron emission of LWR spent fuel is necessary for the back-end of the fuel cycle, such as the dimensioning of transport and storage casks of spent fuel. Although core and depletion codes can calculate the isotopic composition o…
ANALYSIS OF THE FIRST COLIBRI FUEL RODS OSCILLATION CAMPAIGN IN THE CROCUS REACTOR FOR THE EUROPEAN PROJECT CORTEX Open
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 perturb…
CORE SIM+ SIMULATIONS OF COLIBRI FUEL RODS OSCILLATION EXPERIMENTS AND COMPARISON WITH MEASUREMENTS Open
At EPFL, the CROCUS reactor has been used to carry out experiments with vibrating fuel rods. The paper presents a first attempt to employ the measured data to validate CORE SIM+, a neutron noise solver developed at Chalmers University of T…
HIGHLY LOCALIZED AZIMUTHAL MEASUREMENTS IN THE CROCUS REACTOR TOWARDS THE VALIDATION OF HIGH-FIDELITY NEUTRONICS CODES Open
Highly localized in-core measurements are necessary for the validation of neutron transport calculations with high spatial resolution. In the present work, a miniature neutron detector developed at EPFL in collaboration with PSI was used t…
View article: Sea container inspection with tagged neutrons
Sea container inspection with tagged neutrons Open
Neutron inspection of sea-going cargo containers has been widely studied in the past 20 yr to non-intrusively detect terrorist threats, like explosives or Special Nuclear Materials (SNM), and illicit goods, like narcotics or smuggling mate…
VALIDATION OF AXIAL VOID PROFILE MEASURED BY NEUTRON NOISE TECHNIQUES IN CROCUS Open
Recently a joint project has been carried out between the Paul Scherrer Institut, the Ecole Polytechnique Federale de Lausanne and swissnuclear, an industrial partner, in order to determine the axial void distribution in a channel installe…
First tests of a gamma-blind fast neutron detector using a ZnS:Ag-epoxy mixture cast around wavelength-shifting fibers Open
There are many applications for a fast neutron detector with a very low gamma sensitivity such as homeland security, nuclear nonproliferation, and, the main focus of this work, spent nuclear fuel rod characterization and post irradiation e…
Analysis of the first COLIBRI fuel rods oscillation campaign in the CROCUS reactor for the European project CORTEX Open
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 perturb…
CORE SIM+ simulations of COLIBRI fuel rods oscillation experiments and comparison with measurements Open
At EPFL, the CROCUS reactor has been used to carry out experiments with vibrating fuel rods. The paper presents a first attempt to employ the measured data to validate CORE SIM+, a neutron noise solver developed at Chalmers University of T…
A mm<sup>3</sup> Fiber-Coupled Scintillator for In-Core Thermal Neutron Detection in CROCUS Open
This article presents the development, full-characterization, and in-core testing of a miniature neutron detector for the investigation of highly localized in-core neutronics effects in the zero-power reactor CROCUS, operated at the Ecole …
Representativity studies of PROTEUS UO$_2$ fuel for new GEN-III+-type configurations in the EOLE Critical Facility Open
Extended abstract Within the framework of an international collaboration between VENUS, EOLE and PROTEUS experimental teams (VEP), project agreements in the fields of experimental reactor physics design and techniques are proposed to be sh…
Measurement of the Gas Velocity in a Water-Air Mixture in CROCUS Using Neutron Noise Techniques Open
The possibility of measuring the gas-phase velocity in a two-phase mixture through the use of neutron noise techniques is demonstrated in the zero-power reactor CROCUS of the Ecole Polytechnique Federale de Lausanne. It is the first step t…
Assessment of representativity of the PETALE experiments for validation of Swiss LWRs ex-core dosimetry calculations Open
The international experimental program PETALE will be carried out at the CROCUS research reactor of EPFL. The program aims at measuring neutron penetration in slabs made of materials composing typical LWR reactor pressure vessel. The measu…
Neutron noise experiments in the AKR-2 and CROCUS reactors for the European project CORTEX Open
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 t…
Developing and testing a miniature fiber-coupled scintillator for in-core neutron counting in CROCUS Open
An advanced neutron detection system for highly localized measurements in nuclear reactor cores was developed and tested in the Laboratory for Reactor Physics and System Behaviour (LRS) at the École polytechnique fédérale de Lausanne (EPFL…
An Experimental Programme optimized with Uncertainty Propagation: PETALE in the CROCUS Reactor Open
The PETALE experimental programme in the CROCUS reactor at EPFL intends to contribute to the validation and improvement of neutron nuclear data in the MeV energy range for stainless steel, particularly in the prospect of heavy reflector el…
Measurement of the gas velocity in a water-air mixture in crocus by neutron noise technique Open
The possibility to measure the gas phase velocity in a two-component mixture with neutron noise techniques is demonstrated in the zero-power reactor CROCUS of the Ecole Polytechnique Federale de Lausanne. It is the first step toward the ex…