Search Results - "Laureau, A."

Transient coupled calculations of the Molten Salt Fast Reactor using the Transient Fission Matrix approach by Laureau, A., Heuer, D., Merle-Lucotte, E., Rubiolo, P.R., Allibert, M., Aufiero, M.

“…•Neutronic ‘Transient Fission Matrix’ approach coupled to the CFD OpenFOAM code.•Fission Matrix interpolation model for fast spectrum homogeneous…”
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DOSIMETRY MODELING AND EXPERIMENTAL VALIDATION FOR THE PETALE PROGRAM IN THE CROCUS REACTOR by Laureau, A., Lamirand, V., Gruel, A., Frajtag, P., Pautz, A.

“…The PETALE experimental program in the CROCUS reactor intends to provide integral measurements on reactivity worth and dosimetry measurement to constrain…”
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A passive decay heat removal system for emergency draining tanks of molten salt reactors by Wang, Shisheng, Massone, Mattia, Rineiski, Andrei, Merle-Lucotte, E., Laureau, A., Gérardin, D., Heuer, D., Allibert, M.

“…•A new passive decay heat removal system has been invented for molten salt reactor emergency draining tank system.•This system is based on the loop heat pipe…”
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In-core dosimetry for the validation of neutron spectra in the CROCUS reactor by Jiang, Y., Laureau, A., Lamirand, V., Frajtag, P., Pautz, A.

“…The present article describes the preliminary validation study of simulated in-core and reflector n eutron spectra in preparation of oncoming experimental…”
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Beta spectrum shape studies for the predictions of the antineutrino spectrum from reactors by Alcalá, G. A., Algora, A., Fallot, M., Estienne, M., Guadilla, V., Gelletly, W., Beloeuvre, A., Stutzmann, J.-S., Bouvier, S., Eronen, T., Agramunt, J., Bonnet, E., Etasse, D., Giot, L., Laureau, A., Porta, A., Victoria, J. A., Molla, Y.

“…Nuclear reactors antineutrino measurements at short baselines do not fully agree with model predictions calculated with the Conversion Method. An alternative…”
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ANALYSIS OF THE FIRST COLIBRI FUEL RODS OSCILLATION CAMPAIGN IN THE CROCUS REACTOR FOR THE EUROPEAN PROJECT CORTEX by Lamirand, V., Rais, A., Pakari, O., Hursin, M., Laureau, A., Pohlus, J., Paquee, U., Pohl, C., Hübner, S., Lange, C., Frajtag, P., Godat, D., Perret, G., Fiorina, C., Pautz, A.

“…The Horizon2020 European project CORTEX aims at developing an innovative core monitoring technique that allows detecting anomalies in nuclear reactors, such as…”
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CORE SIM+ SIMULATIONS OF COLIBRI FUEL RODS OSCILLATION EXPERIMENTS AND COMPARISON WITH MEASUREMENTS by Mylonakis, A. G., Demazière, C., Vinai, P., Lamirand, V., Rais, A., Pakari, O., Frajtag, P., Godat, D., Hursin, M., Perret, G., Laureau, A., Fiorina, C., Pautz, A.

“…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…”
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THE LiCore POWER PLANT SIMULATOR OF THE MOLTEN SALT FAST REACTOR by Laureau, A., Rosier, E., Merle, E., Beils, S., Bruneau, O., Blanchon, J.C., Gathmann, R., Heuer, D., Passelaigue, F., Vaiana, F., Zanini, A.

“…Molten salt reactors as liquid-fuelled reactors are flexible in terms of operation or design choices, but they are very different in terms of design, operation…”
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Unmoderated molten salt reactors design optimisation for power stability by Laureau, A., Bellè, A., Allibert, M., Heuer, D., Merle, E., Pautz, A.

“…•Eddies in unmoderated Molten Salt Reactor induce unwanted temperature fluctuations.•Temperature variations lead to power fluctuations via Doppler and density…”
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Preliminary thermal–hydraulic core design of the Molten Salt Fast Reactor (MSFR) by Rouch, H., Geoffroy, O., Rubiolo, P., Laureau, A., Brovchenko, M., Heuer, D., Merle-Lucotte, E.

“…•Thermal–hydraulics design of a MSFR core.•Computation Fluid Dynamic (CFD) modelling.•Optimization of the geometry of the MSFR core cavity.•Fuel salt…”
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Spatial analysis of unprotected transients in heterogeneous sodium fast reactors by Laureau, A., Lederer, Y., Krakovich, A., Buiron, L., Fontaine, B.

“…•ULOF and UTOP transient analyses on the sodium fast reactor ASTRID.•Thermal-hydraulics – neutronics coupled calculations.•CEA/IAEC benchmark on spatial and…”
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Transient Fission Matrix: Kinetic calculation and kinetic parameters βeff and Λeff calculation by Laureau, A., Aufiero, M., Rubiolo, P.R., Merle-Lucotte, E., Heuer, D.

“…•Extension of the fission matrix method with a temporal aspect.•A new approach to perform kinetic calculations.•βeff and Λeff kinetic parameters…”
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Calculating the effective delayed neutron fraction in the Molten Salt Fast Reactor: Analytical, deterministic and Monte Carlo approaches by Aufiero, Manuele, Brovchenko, Mariya, Cammi, Antonio, Clifford, Ivor, Geoffroy, Olivier, Heuer, Daniel, Laureau, Axel, Losa, Mario, Luzzi, Lelio, Merle-Lucotte, Elsa, Ricotti, Marco E., Rouch, Hervé

“…•Calculation of effective delayed neutron fraction in circulating-fuel reactors.•Extension of the Monte Carlo SERPENT-2 code for delayed neutron precursor…”
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Transient Fission Matrix: Kinetic calculation and kinetic parameters and calculation by Laureau, A, Aufiero, M, Rubiolo, PR, Merle-Lucotte, E, Heuer, D

“…In this paper, we present a time dependent version of the fission matrix method called Transient Fission Matrix (TFM) that we developed to perform accurate…”
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MIXOPTIM: A tool for the evaluation and the optimization of the electricity mix in a territory by Bonin, Bernard, Safa, Henri, Laureau, Axel, Merle-Lucotte, Elsa, Miss, Joachim, Richet, Yann

“…This article presents a method of calculation of the generation cost of a mixture of electricity sources, by means of a Monte Carlo simulation of the…”
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The role of power sources in the European electricity mix by Bonin, Bernard, Safa, Henri, Thais, Françoise, Laureau, Axel, Merle-Lucotte, Elsa, Miss, Joachim, Matselyuk, Danylo, Richet, Yann, Bréon, François-Marie

“…The ongoing debate in Europe about energy transition enhances the necessity to evaluate the performance of the envisaged mix of power sources, in terms of…”
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A methodology for the identification of the postulated initiating events of the Molten Salt Fast Reactor by Gerardin, Delphine, Uggenti, Anna Chiara, Beils, Stephane, Carpignano, Andrea, Dulla, Sandra, Merle, Elsa, Heuer, Daniel, Laureau, Axel, Allibert, Michel

“…The Molten Salt Fast Reactor (MSFR) with its liquid circulating fuel and its fast neutron spectrum calls for a new safety approach including technological…”
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