Christophe Journeau
Présentation
Publications
Publications
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Aerosol characterization during laser cutting of stainless-steels for underwater, air and nitrogen conditions in the framework of LD-SAFE projectDEM 2024 - International Conference on Decommissioning Challenges: Role and importance of innovations, SFEN - Société Française d'Énergie Nucléaire, May 2024, Avignon, France |
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Airborne particle characterization during mechanical cutting operations of prototypic fuel debris simulantsInternational Topical Workshop on Fukushima-Daiichi Decommissioning Research 2024, Japan Society of Mechanical Engineers - JSME; Atomic Energy Society of Japan - AESJ, Oct 2024, Naraha, Fukushima, Japan |
Characterization of Aerosols Emitted during Core Boring of Prototypic Fukushima Daiichi Fuel Debris SimulantsInternational congress on advances in nuclear power plants - ICAPP 2023, Korean Nuclear Society (KNS); American Nuclear Society (ANS), Apr 2023, Gyeongju, South Korea |
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On the assessment of the risk of aerosol dispersion during laser cutting operations of fuel debris in the 1F2 reactor pedestal and the intended strategies in terms of mitigation meansFDR2022 : International Topical Workshop on Fukushima Decommissioning Research 2022, JSME (Japan Society of Mechanical Engineers), AESJ (Atomic Energy Society of Japan), University of Tokyo, Oct 2022, Nahara, Japan |
Characterization of prototypic corium sample simulating fukushima daiichi unit 2 lower head compositionThe 10th European Review Meeting on Severe Accident Research (ERMSAR2022), ERMSAR, May 2022, Karlsruhe, Germany |
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Development and validation of an agglomeration model for CFD simulations of aerosol dispersion in the frame of Fukushima fuel debris retrievalInternational Topical Workshop on Fukushima Decommissioning Research, FDR2019, May 2019, NARAHA, Japan. pp.690-703, ⟨10.1080/00223131.2020.1862717⟩ |
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Caracterisation de la composition chimique des aerosols issus de la decoupe laser de simulants du coriumCongrès Français sur les Aérosols 2020, CFA, Jan 2020, PARIS, France |
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Temperature ramps for severe accident instrumentation in nuclear reactor cavity concreteSAMMI 2020 - OECD/NEA Specialist Workshop on Advanced Measurement Method and Instrumentation for enhancing Severe Accident Management in an NPP addressing Emergency, Stabilization and Long-term Recovery Phase, OECD; NEA, Dec 2020, Fukushima, Japan. pp.270-273 |
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Long length SPNDs and Distributed Optical Fiber Sensors for Severe Accident remote monitoring and their contribution to Nuclear Safety in the post-Fukushima contextSAMMI 2020 - OECD/NEA Specialist Workshop on Advanced Measurement Method and Instrumentation for enhancing Severe Accident Management in an NPP addressing Emergency, Stabilization and Long-term Recovery Phase, OECD/NEA, Dec 2020, Fukushima, Japan. pp.138-142 |
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Capteurs à fibres optiques répartis pour la surveillance du corium en cas d'accident grave de réacteur nucléaire avec percement de la cuve : le projet ANR RSNR DISCOMSJNOG 2019 - 39e Journées Nationales d’Optique Guidée, Université Paris-Saclay, Jul 2019, Saclay, France |
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Aerosols released during the laser cutting of a Fukushima Daiichi debris simulantThe 9TH European Review Meeting on Severe Accident Research (ERMSAR2019), Mar 2019, Prague, Czech Republic |
Development and validation of agglomeration model for CFD simulations of aerosol dispersion during Fukushima fuel debris retrievalInternational Topical Workshop on Fukushima Decommissioning Research - FDR2019 FDR, May 2019, Naraha, Japan |
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Récupération du corium des réacteurs de Fukushima Dai-ichi : efficacité d'épuration des aérosols produits lors de la découpe au laser sous eau de simulants de corium16ème Congrès Francophone de Techniques Laser pour la mécanique des fluides, CNRS, CentraleSupélec, Université Paris Saclay, IRSN, Sep 2018, Dourdan, France |
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A new experimental R&D program associated with the corium jet impingement on the ASTRID core catcher sacrificial materialInternational Congress on Advances in Nuclear Power Plants (ICAPP 18), Apr 2018, Charlotte, United States |
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Le corium de Fukushima Daiichi : formation, état actuel et R&D en vue de sa récupération16ème Congrès Francophone de Techniques Laser pour la mécanique des fluides, CNRS, CentraleSupélec, Université Paris Saclay, IRSN, Sep 2018, Dourdan, France |
Analysis of aerosol emission and dispersion during the laser cutting of fukushima fuel debris simulants26thInternational Conference on Nuclear Engineering (ICONE - 26), Jul 2018, Londres, United Kingdom. ⟨10.1115/ICONE26-81531⟩ |
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Modelling of x-ray radioscopy for phase topology estimationduring corium sodium interaction26th International Conference on Nuclear Engineering (ICONE - 26), Jul 2018, Londres, United Kingdom |
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Fabricating Fukushima Daiichi in-vessel and ex-vessel fuel debris simulants for the development and qualification of laser cutting techniqueThe 8th European Review Meeting on Severe Accident Research - ERMSAR-2017, May 2017, Varsovie, Poland |
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DISCOMS: DIstributed Sensing for COrium Monitoring and SafetyCANSMART 2015: International Conference on Smart Materials and Structures, Jul 2015, Vancouver, Canada |
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Mixing of Uranium Dioxide an Hafnium at high temperature. Potential application to mitigate criticallity risks in fast reactorsNuMat 2014 - The Nuclear Materials Conference, Oct 2014, Clearwater Beach, United States |
European Nuclear Thermodynamic Database Validated and Applicable in Severe Accident CodesFisa-2003, Symposium on EU Research on Severe Accidents, European Commission, Nov 2003, Luxembourg, Netherlands. pp.ISBN : 92-894-7803-9 |
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European Nuclear Thermodynamic Database Validated and Applicable in Severe Accident CodesFisa-2001, Symposium on EU Research on Severe Accidents, European Commission, Dec 2001, Luxembourg, Netherlands. pp.ISBN : 92-894-3455-4 |
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Distributed corium monitoring in case of severe accident in a Nuclear Power Plant2019 |
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L'étalement du Corium : Hydrodynamique, Rhéologie et Solidification d'un Bain d'Oxydes à Haute TempératureEnergie électrique. Université d'Orléans, 2006. Français. ⟨NNT : ⟩ |
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Contribution des essais en matériaux prototypiques sur la plate-forme PLINIUS à l'étude des accidents graves de réacteurs nucléairesSciences de l'ingénieur [physics]. Université d'Orléans, 2008 |