, Analyse probabiliste du vieillissement-Cas d'étude : La maquette VeRCoRs
,
, Stratégie globale de couplage probabiliste ???????????????????????????????? 5.2.1 Méthodes stochastiques et indicateurs de sensibilité ?????????????????????????
, Les approches de type Monte Carlo ??????????????????????????????????
,
,
, 1.3.1 Méthode de type Galerkin ?????????????????????????????????????
, Approches retenues pour l'analyse probabiliste du comportement THM-F du béton ????????
, Analyse probabiliste du comportement THM-F du béton ?????????
, Distributions des paramètres influents ?????????????????????????????????
,
, Surface de réponse et analyse de sensibilité globale ????????????????????????? 5.3.2.2 Analyse probabiliste??????????????????????????????????????????
,
,
,
, Surface de réponse et analyse de sensibilité globale ????????????????????????? 5.3.5.1.1 Déformations différées ???????????????????????????????????????
, 2.1 Déformations différées ???????????????????????????????????????
,
, Débit d'air sec { travers la masse ???????????????????????????????????. 5.3.6.1.1 Surface de réponse et analyse de sensibilité globale ???????????????????????? 5.3.6.1.2 Analyse probabiliste ?????????????????????????????????????????. 5.3.6.2 Débit d'air sec { travers les ouvertures de fissures ?????????????????????????
, Surface de réponse et analyse de sensibilité globale ???????????????????????? 5.3.6.2.2 Analyse probabiliste ?????????????????????????????????????????
, Analyse fiabiliste du taux de fuite global ???????????????????????????????
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, A fully coupled thermo-hydromechanical model for simulating multiphase flow, deformation and heat transfer in buffer material and rock masses. Rock Mechanics and Mining sciences, A general relation between tensile strength and specimen geometry for concrete-like materials. Materials and constructions, vol.11, pp.187-196, 1977.
, La résistance du béton à très jeune âge, Bulletin LCPC, vol.179, pp.31-41, 1992.
, Comportement au jeune âge du béton: approche 3D du seuil de percolation mécanique. 23 ème rencontres universitaires de GC-risque et environnement. FRANCE, Cement and concrete research, vol.38, issue.6, pp.1183-1197, 1990.
, Couplings in early age concrete from material modeling to structural design, Solids and Structures, vol.35, issue.1-2, pp.4295-4311, 1998.
, Creep and shrinkage coupling: new review of some evidences. Revue Française de Génie Civil, vol.3, pp.3-4, 1999.
, The effect of curing temperature and relative humidity on the strength development of Portland cement mortar. Academic journals. Scientific research and essays, vol.6, pp.2504-2511, 2011.
, Contribution { la caractérisation de l'évolution du taux de fuite des enceintes de confinement du parc nucléaire, Simulation of Hydration and Formation of Structure in Hardening Cement-Based Materials, vol.44, pp.2715-2731, 1980.
, Relation entre formulation d'un béton et propriétés mécaniques, formulation et chaleur d'hydratation, cas de cendres volantes, RILEM, 4th International Symposium On Utilization of HSC/HPC, vol.209, pp.617-642, 1996.
, Sensitivity and Interaction Analysis Based on Sobol' Method and its application in a distributed flood forecasting model, Water Open access Journal, vol.7, pp.2924-2951, 2015.
, A statistical theory of the strength of materials, Proc. of Royal Swedish academy of Engineering science, vol.151, pp.1-45, 1939.
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, Total deformation of loaded drying creep, Cement and Concrete Research, vol.10, pp.601-610, 1980.
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, Quanke S. Sensitivity analysis of the early-age cracking risk in immersed tunnel, Structural concrete, vol.15, issue.2, pp.179-190, 2014.
, One factor at a time designs of resolution V. Statistical planning and inference, vol.131, pp.407-416, 2005.
, A new stochastic approach to transient heat conduction modeling with uncertainty, Heat Mass Transfer, vol.24, issue.2, pp.4681-4693, 2002.
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, Fluid-flow measurements in low permeability media with high pressure gradients using neutron imaging: Application to concrete, Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, vol.114, issue.8, pp.35-42, 1988.
, Effect of specimen sizes, specimen shapes, and placement directions on compressive strength of concrete, Nuclear Engineering and Design, vol.236, issue.2, pp.115-127, 2006.
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, Comportement au jeune âge dans les structures massives. Application au cas de réparation des ouvrages, 2009.
, ? Liste des publications : Journaux scientifiques
, Accounting for realstic THM boundary conditions whilst modeling the ageing of concrete in nuclear containment buildings: model validation and sensitivity analysis. Engineering Structures, vol.166, pp.314-338, 2018.
, New continuous strain-based description of concrete's damage-permeability coupling. Numerical and analytical methods in geomechanics, pp.1-27, 2018.
, Statistical modeling of cracking in large concrete structures under Thermo-Hydro-Mechanical loads: Application to Nuclear Containment Buildings, Nuc. Eng. Des, vol.333, pp.196-223, 2018.
URL : https://hal.archives-ouvertes.fr/hal-01876926
, Statistical modeling of cracking in large concrete structures under Thermo-Hydro-Mechanical loads: Application to Nuclear Containment Buildings. Part 2: Sensitivity analysis, Nuc. Eng. Des, vol.334, pp.1-23, 2018.
URL : https://hal.archives-ouvertes.fr/hal-01876926
, Modeling of ageing effects on the dry air tightness in containment buildingsApplication to nuclear reactors' buildings, 2018.
, Modeling of ageing effects on the dry air tightness in containment buildings-Application to nuclear reactors' buildings. Part 2: PCE-based stochastic approach and reliability analysis, 2018.
, Conférences internationales
, Analyse probabiliste de la fissuration et du confinement des grands ouvrages en béton armé et précontraint-Application aux enceintes de confinement des réacteurs nucléaires (Cas de la maquette VeRCoRs). 36 ème Rencontres Universitaires de Génie Civil (RUGC), Sensitivity analysis of the Thermo-Hydro-Mechanical parameters affecting double walled Nuclear Power Plants behaviour. Proc. of Int. conf. on Structural Mechanics in Reactor Technology (SMIRT). Busan. South Korea, 2017.