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Dive into the research topics where Jean-Charles Jaboulay is active.

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Featured researches published by Jean-Charles Jaboulay.


Nuclear Fusion | 2015

DEMO reactor design using the new modular system code SYCOMORE

C. Reux; L. Di Gallo; F. Imbeaux; P. Bernardi; J. Bucalossi; Guido Ciraolo; Jean-Luc Duchateau; C. Fausser; Davide Galassi; P. Hertout; Jean-Charles Jaboulay; A. Li-Puma; B. Saoutic; Louis Zani; Itm-Tf Contributors

A demonstration power plant (DEMO) will be the next step for fusion energy following ITER. Some of the key design questions can be addressed by simulations using system codes. System codes aim to model the whole plant with all its subsystems and identify the impact of their interactions on the design choices. The SYCOMORE code is a modular system code developed to address key questions relevant to tokamak fusion reactor design. SYCOMORE is being developed within the European Integrated Tokamak Modelling framework and provides a global view (technology and physics) of the plant. It includes modules to address plasma physics, divertor physics, breeding blankets, shield design, magnet design and the power balance of plant. The code is coupled to an optimization framework which allows one to specify figures of merit and constraints to obtain optimized designs. Examples of pulsed and steady-state DEMO designs obtained using SYCOMORE are presented. Sensitivity to design assumptions is also studied, showing that the operational domain around working points can be narrow for some cases.


Computer Physics Communications | 2016

Coupling between a multi-physics workflow engine and an optimization framework

Luc Di Gallo; C. Reux; F. Imbeaux; Jean-François Artaud; Michal Owsiak; Bernard Saoutic; G. Aiello; P. Bernardi; Guido Ciraolo; J. Bucalossi; Jean-Luc Duchateau; Clement Fausser; Davide Galassi; P. Hertout; Jean-Charles Jaboulay; Antonella Li-Puma; Louis Zani

A generic coupling method between a multi-physics workflow engine and an optimization framework is presented in this paper. The coupling architecture has been developed in order to preserve the integrity of the two frameworks. The objective is to provide the possibility to replace a framework, a workflow or an optimizer by another one without changing the whole coupling procedure or modifying the main content in each framework. The coupling is achieved by using a socket-based communication library for exchanging data between the two frameworks. Among a number of algorithms provided by optimization frameworks, Genetic Algorithms (GAs) have demonstrated their efficiency on single and multiple criteria optimization. Additionally to their robustness, GAs can handle non-valid data which may appear during the optimization. Consequently GAs work on most general cases. A parallelized framework has been developed to reduce the time spent for optimizations and evaluation of large samples. A test has shown a good scaling efficiency of this parallelized framework. This coupling method has been applied to the case of SYCOMORE (System COde for MOdeling tokamak REactor) which is a system code developed in form of a modular workflow for designing magnetic fusion reactors. The coupling of SYCOMORE with the optimization platform URANIE enables design optimization along various figures of merit and constraints


Revue des Systèmes | 2016

Quand l’instrumentation de mesure déportée œuvre à l’amélioration de la surveillance du bâtiment réacteur des centrales nucléaires en cas d’accident grave

Pierre Ferdinand; Frédéric Pouillé; Bertrand Ricque; Jean-Michel Bourbotte; Hassen Hamrita; Vladimir Kondrasovs; Hamid Makil; Laurent Maurin; Stéphane Rougeault; Guy Cheymol; Frédéric Damian; Dominique Duval; Jean-Charles Jaboulay; Philippe Le Tutour; Hicham Maskrot; Loïc Barbot; Jean-François Haquet; Christophe Journeau; Quentin Souquet; Jean-François Villard; Grigor Musoyan; Mariya Brovchenko; Isabelle Duhamel; Stéphane Fourrez; Georges Helleux; Laurent Pichon; Youcef Ouerdane

Cet article presente les travaux menes dans le cadre du projet DISCOMS, initie apres Fukushima, et dedie a la surveillance du corium en cas d’Accident Grave (AG) avec percement de la cuve du reacteur. Apres etablissement des objectifs et identification des localisations possibles pour les capteurs, la modelisation des rayonnements a ete menee pour deux generations de reacteurs (le parc en exploitation ‘Gen2’, et ‘Gen3’ soit le reacteur EPR), tant en fonctionnement normal qu’en AG. Eu egard aux conditions extremes de l’interaction corium-beton, une modelisation thermique a diverses profondeurs du radier a ete realisee, afin d’optimiser l’enfouissement des capteurs. Ceci a permis la conception des Collectrons et le choix des fibres optiques monomodes a meme de resister a la temperature et a la dose pendant les 60 ans de fonctionnement, suivis d’un AG. Grâce a des tests en irradiateur, plusieurs fibres optiques presentant une faible attenuation induite ont ete qualifiees pour leur mise en câble. Celles-ci seront interrogeables par plusieurs instruments (OTDR, DTS, BOTDA, OFDR), dont les performances ont ete etablies. Pour les Collectrons, les etudes ont montre que l’AG etait detectable via la mesure de leur courant auto-genere. S’en suivit le developpement d’une electronique multivoie a bas niveau de courant, et d’une perche mixte collectrons -thermocouple, de grande longueur, contenant un premier Collectron Rhodium pour flux neutronique (fonctionnement normal), un second de type Platine pour les neutrons et γ (Accident Grave), et un thermocouple de type K. Le projet va se poursuivre, jusqu’a la validation globale, et in fine par un essai ‘Vulcano’ de coulee de corium sur une dalle de beton. Une fois la faisabilite assuree, le deploiement de cette solution innovante pourrait etre envisage.


Fusion Engineering and Design | 2016

Neutronic performance issues of the breeding blanket options for the European DEMO fusion power plant

Ulrich Fischer; C. Bachmann; Jean-Charles Jaboulay; F. Moro; I. Palermo; P. Pereslavtsev; R. Villari


Fusion Engineering and Design | 2013

Neutronic predesign tool for fusion power reactors system assessment

Jean-Charles Jaboulay; A. Li Puma; J. Martínez Arroyo


Fusion Engineering and Design | 2016

Status on DEMO Helium Cooled Lithium Lead breeding blanket thermo-mechanical analyses

J. Aubert; G. Aiello; Jean-Charles Jaboulay; B. Kiss; A. Morin


Fusion Engineering and Design | 2014

TRIPOLI-4® Monte Carlo code ITER A-lite neutronic model validation

Jean-Charles Jaboulay; Pierre-Yves Cayla; Clement Fausser; Frédéric Damian; Yi-Kang Lee; Antonella Li Puma; Jean-Christophe Trama


Fusion Engineering and Design | 2017

Thermo-mechanical analyses and ways of optimization of the helium cooled DEMO First Wall under RCC-MRx rules

J. Aubert; G. Aiello; P. Arena; Rémi Boullon; Jean-Charles Jaboulay; A. Morin


Nuclear Fusion | 2017

Design of the helium cooled lithium lead breeding blanket in CEA: from TBM to DEMO

G. Aiello; J. Aubert; Laurent Forest; Jean-Charles Jaboulay; A. Li Puma; L.V. Boccaccini


Fusion Engineering and Design | 2017

Nuclear analysis of the HCLL blanket for the European DEMO

Jean-Charles Jaboulay; G. Aiello; J. Aubert; Alexandro Morin; Marc Troisne

Collaboration


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G. Aiello

Université Paris-Saclay

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J. Aubert

Université Paris-Saclay

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A. Morin

Université Paris-Saclay

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Rémi Boullon

Université Paris-Saclay

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Davide Galassi

Aix-Marseille University

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Ulrich Fischer

Karlsruhe Institute of Technology

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Laurent Forest

Université Paris-Saclay

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L.V. Boccaccini

Karlsruhe Institute of Technology

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