Concept
Nuclear reactor core
Publications associées (36)
Intra-pin Reaction Rate Measurements in the CROCUS Experimental Reactor
Andreas Pautz, Vincent Pierre Lamirand, Mathieu Hursin, Oskari Ville Pakari, Thomas Jean-François Ligonnet, Tom Mager
In response to the need for validating high-fidelity deterministic neutronics solvers capable of providing pin-resolved neutron flux distributions, intra-pin reaction rates measurements were performed in the CROCUS experimental reactor. A specially designe ...
2024Design of an Instrumented Fuel Rod for Intra-pin Neutron Flux Measurements in the CROCUS Experimental Reactor
Andreas Pautz, Vincent Pierre Lamirand, Mathieu Hursin, Thomas Jean-François Ligonnet, Tom Mager, Won Dong Shin
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 ...
2023Extension of GeN-Foam to departure from nucleate boiling prediction and validation against the OECD/NRC PSBT benchmark
Carlo Fiorina, Yuhang Niu, Hao Qin
The prediction of departure from nucleate boiling (DNB) has always been a crucial aspect of thermal-hydraulic codes for the analysis of Light Water Reactors. In this paper, GeN-Foam, a multi-physics code developed based on OpenFOAM, has been enhanced to in ...
Lausanne2023Unmoderated molten salt reactors design optimisation for power stability
Andreas Pautz, Axel Guy Marie Laureau, Andrea Bellè
The critical region of unmoderated molten salt reactors consists in a cavity filled with a liquid fuel. The lack of internal structure implies a complex flow structure of the circulating fuel salt. A preliminary core shape optimization has been performed d ...
PERGAMON-ELSEVIER SCIENCE LTD2022Optimisation of used nuclear fuel canister loading using a neural network and genetic algorithm
Andreas Pautz, Hakim Ferroukhi, Dimitri Rochman, Alexander Vasiliev
This paper presents an approach for the optimisation of geological disposal canister loadings, combining high resolution simulations of used nuclear fuel characteristics with an articial neural network and a genetic algorithm. The used nuclear fuels (produ ...
SPRINGER LONDON LTD2021Towards the Validation of Noise Experiments in the CROCUS Reactor Using the TRIPOLI-4 Monte Carlo Code in Analog Mode
Andreas Pautz, Vincent Pierre Lamirand, Oskari Ville Pakari
Intrinsic neutron noise experiments offer a non-invasive manner to measure the prompt decay constant or reactivity of fissile systems. Using the fluctuations in the density of fission chains, one can infer the kinetics parameters via correlation analysis s ...
2021Development of Advanced Methodologies for Monitoring and Modelling of Neutron Noise in Modern LWR Cores
Nuclear reactors are inherently stochastic systems, in which neutronic and thermal-hydraulic parameters fluctuate continuously even during steady-state conditions. In addition, structural components vibrate due to the coolant hydraulic forces. This stochas ...
EPFL2020Design and Simulation of Gamma Spectrometry Experiments in the CROCUS Reactor
Andreas Pautz, Vincent Pierre Lamirand, Mathieu Hursin, Oskari Ville Pakari, Fanny Vitullo
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 ...
E D P SCIENCES2020Towards the validation of neutron noise simulators: qualification of data acquisition systems
Andreas Pautz, Vincent Pierre Lamirand, Mathieu Hursin, Oskari Ville Pakari, Axel Guy Marie Laureau, Adolfo Rais
This paper deals with the processes involved in the generation of reliable experimental data for the validation of computer simulations. In the field of neutron noise, the analysis of results is based on spectral features of the detector signals in the fre ...
2019Extension of the nodal code DYN3D to SFR applications
DYN3D is a well-established Light Water Reactor (LWR) simulation tool and is being extended for safety analyses of Sodium cooled Fast Reactors (SFRs) at the Helmholtz-Zentrum Dresden-Rossendorf. This thesis focuses on the first stage of the development pro ...
EPFL2019