Vincent Lamirand
EPFL SB IPHYS LRS
PH D3 475 (Bâtiment PH)
Station 3
1015 Lausanne
+41 21 693 33 46
Office: PH D3 475
EPFL › SB › IPHYS › LRS
Site web: https://lrs.epfl.ch/
+41 21 693 33 46
EPFL › SB › SB-SPH › SPH-ENS
Site web: https://sph.epfl.ch/
+41 21 693 33 46
EPFL › SB › SB-DEC › CF-SB
Site web: https://sb.epfl.ch/conseil
+41 21 693 33 46
EPFL › P › P-EM › AE
Site web: https://ae.epfl.ch/
Expertise
Expertise
Mission
Je suis actuellement membre du Conseil de Faculté des Sciences de base, et ce depuis 2016.
Formation
2011 – 2011
UJF Grenoble 1 (France)
Dirigée par
Prof. Eric Liatard (eric.liatard@lpsc.in2p3.fr),
Dr. Vincent Gressier (vincent.gressier@irsn.fr)
2008 – 2008 UCB Lyon 1 (France)
2006 – 2006 UCB Lyon 1 (France)
Expériences professionnelles
A Monte Carlo Perspective on Reactor Kinetics: From Static and Dynamic Reactivity to Time-Dependent Simulations
Nuclear Science and Engineering. 2025. DOI : 10.1080/00295639.2025.2586414.Investigation of Noise Detection Systems in the CROCUS Reactor from SANDcaStLE
2025. 9th Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA 2025), Valencia, Spain, 2025-06-09 - 2025-06-13. DOI : 10.1051/epjconf/202533804015.Comparison of high-fidelity transport code predictions against the NECTAR intra-pin reaction rate measurements
Annals of Nuclear Energy. 2025. DOI : 10.1016/j.anucene.2025.111430.Measurement of the Prompt Neutron Decay Constant in a Zero-Power Reactor Using a Novel 3D Detector System
NUCLEAR SCIENCE AND ENGINEERING. 2025. DOI : 10.1080/00295639.2025.2456411.CORTEX experiments – Part I: Modulation campaigns in AKR-2 & CROCUS for the validation of neutron noise codes
Annals of Nuclear Energy. 2025. DOI : 10.1016/j.anucene.2024.110928.Welch Method and Bootstrapping Applied to Subcritical Gamma Noise
NUCLEAR SCIENCE AND ENGINEERING. 2025. DOI : 10.1080/00295639.2024.2445469.Simulations of a new neutron imaging station at the CROCUS zero power reactor
EPJ Web of Conferences. 2025. DOI : 10.1051/epjconf/202533804012.HONEY: High-Resolution Reactor Kinetics experiments in the CROCUS reactor
EPJ Web of Conferences. 2025. DOI : 10.1051/epjconf/202533804002.Towards the Direct Observation of Xenon-135 Poisoning in a Zero-Power Reactor via Gamma Spectroscopy
EPJ Web of Conferences. 2025. DOI : 10.1051/epjconf/202533804010.Pile-oscillation results for stainless steel with local and 3D global measurements
EPJ Web of Conferences. 2025. DOI : 10.1051/epjconf/202533804004.Design and testing of a fiber-coupled fast neutron scintillation detector for low-power research reactors
EPJ Web of Conferences. 2025. DOI : 10.1051/epjconf/202533804003.Revisiting the reactor period capabilities in TRIPOLI-4®
2025. International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Denver, US, 2025-04-27 - 2025-04-30. p. 1166 - 1175. DOI : 10.13182/MC25-47121.From real life to scale model (and back again): The life of CROCUS in the student’s mind
EPJ Web of Conferences. 2025. DOI : 10.1051/epjconf/202533811002.Analysis and Reproduction of Stainless-steel Integral Experiments Towards Nuclear Data Assimilation
Lausanne, EPFL, 2025. DOI : 10.5075/epfl-thesis-11638.Adaptive adjoint-based population-control methods for kinetic simulations in TRIPOLI-4
EPJ Nuclear Sciences & Technologies. 2025. DOI : 10.1051/epjn/2025069.CORTEX experiments, Part III: Experimental determination of the zero power transfer function of AKR-2 with reliable uncertainties
Annals of Nuclear Energy. 2024. DOI : 10.1016/j.anucene.2024.110686.CORTEX experiments, Part II: Postprocessing of neutron noise time series to determine reliable mean and uncertainties
Annals of Nuclear Energy. 2024. DOI : 10.1016/j.anucene.2024.110704.Revision of PSI calculation capabilities and validation experience on the BEPU-type reactor dosimetry applications
2024. 17 International Symposium on Reactor Dosimetry (Part II), Lausanne, Switzerland, 2023-05-21 - 2023-05-26. DOI : 10.1051/epjconf/202430803011.Towards a highly efficient and unbiased population-control algorithm for kinetic Monte Carlo simulations
2024. Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo, Paris, France, 2024-10-20 - 2024-10-24. DOI : 10.1051/epjconf/202430209006.Fast simulation of neutron noise using the Transient Fission Matrix approach and validation on the CROCUS reactor
2024. Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo, Paris, France, 2024-10-20 - 2024-10-24. DOI : 10.1051/epjconf/202430208002.Neutron-Gamma Noise Measurements in a Zero-Power Reactor Using Organic Scintillators
Ieee Transactions On Nuclear Science. 2024. DOI : 10.1109/TNS.2023.3337657.Gamma-ray Spectroscopy in Low-Power Nuclear Research Reactors
Journal Of Nuclear Engineering. 2024. DOI : 10.3390/jne5010003.High-Resolution Modeling Without Computation Slowdown for PETALE in CROCUS
Nuclear Science and Engineering. 2024. DOI : 10.1080/00295639.2024.2357963.Intra-pin Reaction Rate Measurements in the CROCUS Experimental Reactor
IEEE Transactions on Nuclear Science. 2024. DOI : 10.1109/TNS.2024.3370371.Design of an Open-Loop Pile-Oscillation Program in the CROCUS Reactor
IEEE Transactions on Nuclear Science. 2024. DOI : 10.1109/TNS.2024.3371183.Measurement of the Prompt Decay Constant in a Zero Power Reactor Using a Novel 3D Detector System
2024. International Conference on Physics of Reactors, San Francisco, United States, 2024-04-21 - 2024-04-24. p. 155 - 163. DOI : 10.13182/PHYSOR24-43877.Large volume dosimetry for BLOOM in CROCUS
2024Gamma noise to non-invasively monitor nuclear research reactors
Scientific Reports. 2024. DOI : 10.1038/s41598-024-59127-y.Sub-critical gamma noise measurements in the CROCUS zero-power reactor
2024. International Conference on Physics of Reactors, San Francisco, United States, 2024-04-21 - 2024-04-24. p. 118 - 127. DOI : 10.13182/PHYSOR24-43501.Modeling noise experiments performed at AKR-2 and CROCUS zero-power reactors
Annals Of Nuclear Energy. 2023. DOI : 10.1016/j.anucene.2023.110066.Development of a multi-channel gamma-blind fast neutron detector based on wavelength shifting fibers embedded in a ZnS:Ag epoxy mixture
Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2023. DOI : 10.1016/j.nima.2023.168385.Analysis of the preliminary campaign for the PETALE program
Epj Nuclear Sciences & Technologies. 2023. DOI : 10.1051/epjn/2023010.Design of an Instrumented Fuel Rod for Intra-pin Neutron Flux Measurements in the CROCUS Experimental Reactor
EPJ Web of Conferences. 2023. DOI : 10.1051/epjconf/202328804007.High accuracy measurement of the prompt neutron decay constant in CROCUS using Gamma Noise and bootstrapped uncertainties
Annals Of Nuclear Energy. 2022. DOI : 10.1016/j.anucene.2022.109011.Characterization of High Harmonic Frequencies in Reactor Noise Experiments Within the CORTEX Project
IEEE Transactions on Nuclear Science. 2022. DOI : 10.1109/TNS.2022.3143238.Miniature and Minimalistic Neutron Detectors for Online High-Resolution Experiments in the Zero-Power Reactor CROCUS
Lausanne, EPFL, 2022. DOI : 10.5075/epfl-thesis-9492.Millimetric fuel rod displacements: an experimental study of the impact on local thermal neutron flux in the CROCUS reactor
2022. International Conference on Physics of Reactors, Pittsburgh, United States, 2022-05-15 - 2022-05-20. p. 2632 - 2641. DOI : 10.13182/PHYSOR22-37846.Modeling the response of a diamond detector in the zero power reactor CROCUS
European Physical Journal Plus. 2021. DOI : 10.1140/epjp/s13360-021-02230-0.Delayed gamma fraction determination in the zero power reactor CROCUS
Epj Nuclear Sciences & Technologies. 2021. DOI : 10.1051/epjn/2021015.Preliminary analysis of the PETALE program and comparison to simulations
2021Extension of miniature neutron scintillators features in CROCUS: novel acquisition scheme and extended flux range
2021Investigation of the Fission Matrix methodology using the Monte Carlo code Serpent 2 and application to the CROCUS reactor
2021Local and high distance neutron and gamma measurements of fuel rods oscillation experiments
2021. Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), Prague, CZECH REPUBLIC, Jun 21-25, 2021. DOI : 10.1051/epjconf/202125304024.PISTIL, a reactivity modulation device to probe the transfer function of the nuclear reactor CROCUS
2021. Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), Prague, CZECH REPUBLIC, Jun 21-25, 2021. DOI : 10.1051/epjconf/202125304007.First in-core gamma spectroscopy experiments in a zero power reactor
2021. Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), Prague, CZECH REPUBLIC, Jun 21-25, 2021. DOI : 10.1051/epjconf/202125304022.Design of a 150-miniature detectors 3D core-mapping system for the CROCUS reactor
2021. Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), Prague, CZECH REPUBLIC, Jun 21-25, 2021. DOI : 10.1051/epjconf/202125304023.High resolution measurements with miniature neutron scintillators in the SUR-100 zero power reactor
2021. Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), Prague, CZECH REPUBLIC, Jun 21-25, 2021. DOI : 10.1051/epjconf/202125304029.Kilogram-Scale Crystallogenesis of Halide Perovskites for Gamma-Rays Dose Rate Measurements
Advanced Science. 2020. DOI : 10.1002/advs.202001882.Review of kinetic modulation experiments in low power nuclear reactors
Epj Nuclear Sciences & Technologies. 2020. DOI : 10.1051/epjn/2020017.The Unscented Kalman Filter: Introduction and Application to Point Reactor Kinetics
2020Uncertainty propagation for the design study of the PETALE experimental programme in the CROCUS reactor
Epj Nuclear Sciences & Technologies. 2020. DOI : 10.1051/epjn/2020004.Uncertainty propagation based on correlated sampling technique for nuclear data applications
Epj Nuclear Sciences & Technologies. 2020. DOI : 10.1051/epjn/2020003.A mm(3) Fiber-Coupled Scintillator for In-Core Thermal Neutron Detection in CROCUS
Ieee Transactions On Nuclear Science. 2020. DOI : 10.1109/TNS.2020.2977530.Measurement of the Gas Velocity in a Water-Air Mixture in CROCUS Using Neutron Noise Techniques
Nuclear Technology. 2020. DOI : 10.1080/00295450.2019.1701906.Validation of the Serpent 2 model for the CARROUSEL facility
2020Developing and testing a miniature fiber-coupled scintillator for in-core neutron counting in CROCUS
2020. 6th International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), Portoroz, SLOVENIA, Jun 17-21, 2019. DOI : 10.1051/epjconf/202022504018.Power calibration methodology at the CROCUS reactor
2020. 6th International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), Portoroz, SLOVENIA, Jun 17-21, 2019. DOI : 10.1051/epjconf/202022504022.Experimental and numerical study of stochastic branching noise in nuclear reactors
Lausanne, EPFL, 2020. DOI : 10.5075/epfl-thesis-8336.Neutron noise experiments in the AKR-2 and CROCUS reactors for the European project CORTEX
2020. 6th International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), Portoroz, SLOVENIA, Jun 17-21, 2019. DOI : 10.1051/epjconf/202022504023.Noise analysis techniques of in-core modulation experiments of the European CORTEX project
2020. 29th International Conference Nuclear Energy for New Europe (NENE 2020), Portorož, Slovenia, September 7–10, 2020. p. 212.1 - 212.8.Assessment of representativity of the PETALE experiments for validation of Swiss LWRs ex-core dosimetry calculations
2020. International Conference on Nuclear Data for Science and Technology (ND), Beijing, PEOPLES R CHINA, May 19-24, 2019. DOI : 10.1051/epjconf/202023922001.Towards the validation of neutron noise simulators: qualification of data acquisition systems
2019. International Conference on Mathematics and Computational Methods applied to Nuclear Science and Engineering (M&C 2019), Portland, OR, USA, August 25-29, 2019.An Experimental Programme optimized with Uncertainty Propagation: PETALE in the CROCUS Reactor
2019. WONDER 2018 : 5th International Workshop On Nuclear Data Evaluation for Reactor applications, Aix-en-Provence, France, October 8-12, 2018. DOI : 10.1051/epjconf/201921103003.Measurement of the gas velocity in a water-air mixture in crocus by neutron noise technique
2019. International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019), Portland, OR, USA, August 25-29, 2019.Determination of the activity inventory and associated uncertainty quantification for the CROCUS zero power research reactor
Annals of Nuclear Energy. 2019. DOI : 10.1016/j.anucene.2019.107034.Kinetic Parameter Measurements in the CROCUS Reactor Using Current Mode Instrumentation
Ieee Transactions On Nuclear Science. 2018. DOI : 10.1109/TNS.2018.2831180.Design of Separated Element Reflector Experiments in CROCUS: PETALE
2018. 16th International Symposium on Reactor Dosimetry, Santa Fe, NM, May 07-12, 2017. p. 1 - 14. DOI : 10.1520/STP760820170090.Total Monte Carlo acceleration for the PETALE experimental programme in the CROCUS reactor
2018. WONDER 2018 : 5th International Workshop On Nuclear Data Evaluation for Reactor applications, Aix-en-Provence, France, October 8-12, 2018. DOI : 10.1051/epjconf/201921103002.Investigation of spatial effects on neutron noise measurements in the zero power reactor CROCUS
2018. PHYSOR 2018: Reactor Physics paving the way towards more efficient systems, Cancún, Mexico, April 22-26, 2018.Intercomparison of neutron noise measurement systems in the CROCUS reactor
2018. PHYSOR 2018: Reactor Physics paving the way towards more efficient systems, Cancún, Mexico, April 22-26, 2018.Design of Separated Element Reflector Experiments in CROCUS: PETALE
2017. ISRD16 International Symposium on Reactor Dosimetry, Santa Fe, New Mexico, USA, May 7-12, 2017.Future experimental programmes in the CROCUS reactor
2016. RRFM/IGORR 2016, Berlin, Germany, March 13-17, 2016. p. 284 - 292. DOI : 10.13140/RG.2.1.2309.6728.Correction factors to apply to fission rates measured by miniature fission chambers in various neutron spectra
2014. IGORR Conference 2014, San Carlos de Bariloche, Argentina, November 17-21, 2014. DOI : 10.13140/RG.2.1.3106.3923.Enseignement et PhD
Doctorant·es actuel·les
Alexis Paul Boris Claude Dupont-Bembinoff
A co-dirigé les thèses EPFL de
Oskari Ville Pakari, Fanny Vitullo, Thomas Jean-François Ligonnet
Cours
Radiation and reactor experiments
PHYS-451
Le cours a pour but principal de familiariser les étudiant-e-s aux différentes techniques expérimentales de détection des radiations ionisantes et aux mesures expérimentales sur un réacteur nucléaire. Les mesures sont effectuées sur CROCUS, le réacteur de l'EPFL.
Radiation detection
PHYS-452
Ce cours est dédié à la détection de rayonnements ionisants dans le domaine en énergie keV-MeV. Cela inclut : 1- la physique des interactions rayonnement-matière, 2- les différentes étapes d'un processus de détection, 3- les détecteurs, instrumentations et méthodes de mesure couramment employés.