WorldCat Identities

Seiler, Jean-Marie

Overview
Works: 13 works in 18 publications in 2 languages and 25 library holdings
Roles: Author, Opponent, Thesis advisor
Classifications: QC776, 620
Publication Timeline
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Most widely held works by Jean-Marie Seiler
Étude de l'ébullition du sodium au cours d'un transitoire rapide de puissance dans un canal chauffant : travail effectué dans le cadre de la sûreté des réacteurs à neutrons rapides by Jean-Marie Seiler( Book )

5 editions published in 1977 in French and held by 9 WorldCat member libraries worldwide

PHYSIQUE DE L'EBULLITION DU SODIUM. ETUDE EXPERIMENTALE. APPROCHE THEORIQUE. INTERPRETATION DES EXPERIENCES
Interaction corium-béton : étude du transfert de chaleur en écoulement diphasique by Milan Amižić( )

1 edition published in 2014 in English and held by 2 WorldCat member libraries worldwide

Dans le cadre de la recherche sur les accidents graves pour la deuxième et la troisième génération de réacteurs nucléaires, certains aspects de l'ablation de béton dans le puits de cuve au cours de l'interaction corium-béton (ICB) restent encore inexpliquées. La détermination d'échange de chaleur le long de la région interfaciale entre un bain de corium et un béton est importante pour l'évaluation de la progression d'ablation du béton et, éventuellement, la percée de fondation. Le projet CLARA s'inscrit une recherche expérimentale sur la thermohydraulique au sein d'un bain de liquide agitée par des bulles de gaz. Les essais CLARA sont réalisés avec des matériaux simulants. Ils permettent de mettre en évidence l'influence de la vitesse superficielle du gaz, de la viscosité du liquide et de la géométrie sur le coefficient d'échange de chaleur entre le bain de liquide chauffé et les parois verticales et horizontales de la piscine qui sont maintenues à une température uniforme. La première campagne d'essais a été réalisée avec la configuration du bain de petite taille (50 cm × 25 cm × 25 cm). Les essais ont été réalisés avec des liquides couvrant un large éventail de viscosité dynamique, d'environ 1 mPa s à 10000 mPa s. La vitesse superficielle du gaz est modifiée jusqu'à 8 cm/s. Cette thèse comporte une brève description de la phénoménologie de l'ICB, une synthèse bibliographique sur les corrélations d'échange de chaleur existantes pour l'écoulement diphasique et le taux de vide, une description de l'installation CLARA, les résultats des essais et leur interprétation. Les résultats expérimentaux sont comparés avec les modèles existants et certains nouveaux modèles pour l'évaluation du coefficient d'échange de chaleur dans un écoulement diphasique
Modélisation d'un transitoire de perte de débit primaire non protégé dans un RNR-Na by Jean-Baptiste Droin( )

1 edition published in 2016 in French and held by 2 WorldCat member libraries worldwide

Within the framework of the Generation IV Sodium-cooled Fast Reactor (SFR) R&D program of CEA (French Commissariat à l'Energie Atomique et aux Energies Alternatives), safety in case of severe accidents is assessed.Such transients are usually simulated with mechanistic codes (such as SAS-SFR and SIMMER III). As a complement to these codes, which give reference accidental transient calculations, a new physico-statistical approach is currently followed by the CEA; its final objective being to derive the variability of the main results of interest for safety. This approach involves a fast-running description of extended accident sequences coupling physical models for the main phenomena to advanced statistical analysis techniques. It enables to perform a large number of simulations in a reasonable computational time and to describe all the possible bifurcations of the accident transient.In this context, this PhD work presents the physical tool (models and results assessment) dedicated to the initiation and primary phases of an Unprotected Loss Of Flow accident (i.e. until the end of sub-assemblies degradation and before large molten pools formation). The accident phenomenology during these phases is described and illustrated by numerous experimental evidences.It is underlined that the features of the new heterogeneous core concept (called CFV of the French ASTRID prototype) leads to different kinds of ULOF transients than those occurring in the previous past homogeneous cores (SuperPhenix, Phenix...). Indeed, its negative void effect drops the nuclear power when sodium heats-up and possibly boils. This enables three types of ULOF transients characterized by various core final states; the first two types leading to final coolable core states in natural circulation flow (the first one in single phase, the second one in stabilized two-phase flow) whereas the core undergoes a flow excursion followed by sub-assemblies degradation in the last type. In this study, a particular attention is paid to stabilize boiling occurrence which leads to minimize severe accident consequences.The phenomena occurring during the various ULOF transients are modelled in accordance to the level of details required to catch all the possible bifurcations of the transient. The tool coupled different (2D, 1D and 0D) models of thermics, thermo-hydraulics, core degradation (material melting and motions) and neutronics. The assumptions associated to these models are highlighted, discussed and validated. The physical tool capability of simulating the various realistic ULOF transients (without boiling, with stabilized boiling or flow excursion after boiling) is demonstrated by comparisons to experimental results (GR19, SCARABEE experiments) and to mechanistic simulations (CATHARE2 and SIMMER III).Parametric studies are then carried out on two variables: the fuel burn-up and the model of neutronic feedbacks. They underline the important influence of these parameters on the transient and the final core state. Finally, a preliminary sensitivity analysis (2000 simulations) is performed on 26 uncertain parameters (linked to initial core configuration, accident features, model uncertainties and radial nodalization). The variability of the final core state is underlined and quantified; only around 25% of cases lead to core degradation. The main influent parameters on transient phenomena are also identified, enabling to prioritize core design and safety studies.In the future, this tool will be used for safety-informed design and stability analyses of fast reactor systems, allowing to emphasize the main dominant phenomena and trends of significance for safety assessment
Transferts de chaleur et de masse dans un bain liquide avec fusion de la paroi et effets de composition by Quynh Trang Pham( )

1 edition published in 2013 in French and held by 2 WorldCat member libraries worldwide

This work deals with the thermal-hydraulics of a melt pool coupled with the physical chemistry for thepurpose of describing the behaviour of mixtures of materials (non-eutectic).Evolution of transient temperature in a liquid melt pool heated by volumetric power dissipation hasbeen described with solidification on the cooled wall. The model has been developed and is validatedfor the experimental results given by LIVE experiment, performed at Karlsruhe Institute ofTechnology (KIT) in Germany. Under the conditions of these tests, it is shown that the interfacetemperature follows the liquidus temperature (corresponding to the composition of the liquid bath)during the whole transient. Assumption of interface temperature as liquidus temperature allowsrecalculating the evolution of the maximum melt temperature as well as the local crust thickness.Furthermore, we propose a model for describing the interaction between a non-eutectic liquid meltpool (subjected to volumetric power dissipation) and an ablated wall whose melting point is below theliquidus temperature of the melt. The model predictions are compared with results of ARTEMIS 2Dtests. A new formulation of the interface temperature between the liquid melt and the solid wall(below liquidus temperature) has been proposed
Etude du renoyage par le haut en cas d'accident grave et en particulier oxydation des mélanges (U, Zr, O) by Estelle Brunet-Thibault( Book )

2 editions published in 2006 in French and held by 2 WorldCat member libraries worldwide

In 1979, the Three Mile Island (TMI) accident occurred in United States and accelerated research activities in the field od severe accidents. Severe accident management procedures imply massive water injections to flood the core. The work of this thesis bent pricipally over this reflooding. The first part of the study concems the core oxidation enhancement during the reflooding phase which leads to a rough increase of the concentration ofbumable hydrogen in the containment. This is why the study carried on the analysis of the contribution of the oxidation of U-Zr-O mixtures, towards the total production ofhydrogen during reflooding. In the second part, the study concems top flooding modelling i.e. : with injection of water in the hot legs. Here, we attempted to define bases and realize a model allowing to describe this type of reflooding. These models were validated on the simulation of the PARAMETER with MAAP4 code
Approche thermodynamique des transformations de la biomasse by Guillaume Boissonnet( Book )

1 edition published in 2003 in French and held by 1 WorldCat member library worldwide

Analyse environnementale de l'utilisation de biomasse pour la production de tuyaux en fonte by Gaël Fick( )

1 edition published in 2013 in French and held by 1 WorldCat member library worldwide

Les émissions élevées de CO2 de la filière industrielle de fabrication des tuyaux en fonte résultent pour l'essentiel de l'emploi massif de carbone fossile, charbon et coke, comme combustible et agent réducteur dans les procédés. Substituer du carbone issu de biomasse au carbone fossile en vue de réduire ces émissions de CO2, avec application au cas d'une usine lorraine, a été l'idée de départ de ce travail. Différents types de biomasse ont été envisagés. Le bois et la paille seraient localement disponibles en quantité suffisante pour autoriser une substitution partielle de 20 % du coke. Cette biomasse doit cependant être traitée thermiquement (séchage et pyrolyse) avant de satisfaire les spécifications techniques imposées par les procédés métallurgiques (agglomération, cokerie, haut fourneau). Six scénarios d'usage de la biomasse au haut fourneau ou à l'agglomération ont été sélectionnés. Pour les évaluer sur la base de leur mérite environnemental, nous avons réalisé une analyse de cycle de vie comparative en suivant une approche du type berceau à la porte. Point original de notre étude, l'inventaire de cycle de vie est issu de modèles systémiques des principaux procédés, spécifiquement développés et intégrés à un logiciel de diagrammes de flux. Grâce à ces modèles et notamment celui du haut fourneau, on a pu déterminer les taux de remplacement du coke par trois types de biomasse (charbon de bois en blocs, charbon de bois pulvérisé, bois torréfié pulvérisé) et prédire les modifications de fonctionnement qu'entrainerait l'injection de biomasse. Les résultats de l'analyse de cycle de vie montrent que l'injection de bois, carbonisé ou torréfié, sous forme pulvérisée aux tuyères du haut fourneau serait une solution intéressante d'un point de vue environnemental : baisse des émissions de gaz à effet de serre (-15 %) et des impacts sur la santé humaine et sur les écosystèmes. A l'heure actuelle cependant, le coût économique d'une telle solution demeure excessif
Nuclear materials : structural materials modeling and simulation( Book )

1 edition published in 2019 in English and held by 1 WorldCat member library worldwide

Neutronics by Jean-François Parisot( Book )

1 edition published in 2015 in English and held by 1 WorldCat member library worldwide

"Neutronics (or neutron physics) is the study of neutrins travelling through matter, of conditions for a chain reaction, and of changes in matter's composition due to nuclear reactions. It makes it possible to design and operate nuclear reactors and fuel cycle facilities."--Publisher
Effets matériaux sur les phénomènes multiphasiques produisant lors des phases avancées d'accident grave de réacteur nucléaire by Jean-Marie Seiler( Book )

1 edition published in 2003 in English and held by 1 WorldCat member library worldwide

Etude du comportement des espèces inorganiques dans une installation de gazéification de la biomasse : condensation des aerosols et dépôts by Martin Petit( )

1 edition published in 2011 in French and held by 1 WorldCat member library worldwide

The aim of this work is to analyse theoretically and experimentally inorganic species conden- sation in a biomass gasification facility. During biomass gasification, some inorganic species are volatilised and then condense when the syngas cools down. These species can spoil the facility and thus have to be removed before the biodiesel synthesis. First, a thermodynamic study descri- bed the nature and distribution of inorganic species either volatilised during biomass gasification or condensed during cooling. Then an aerosol condensation model for biomass gasification has been developed using a mathematical description of the different phenomena involved (nuclea- tion, growth, agglomeration, deposition). Meanwhile, an experimental device (ANACONDA) has been built and qualified. This device was used to analyse KCl condensation on graphite particles as the gas cooled at 1000 K/s. Experimental results showed nucleation of new KCl particles du- ring the cooling, KCl condensation on graphite particles and deposition of KCl and particles on walls. KCl condensation causes an increase in graphite particle aerodynamic diameter. Graphite particles prevent wall deposit of KCl, which decreased from 40% to 25%. From the comparison of simulation and experimental results, the various phenomena could be quantified and the model validated. Finally, the model was used to propose solutions for limiting inorganic deposit on exchanger walls in a biomass-gasification industrial facility
Clean-up & dismantling of nuclear facilities( Book )

1 edition published in 2018 in English and held by 1 WorldCat member library worldwide

Modélisation de l'interaction entre le cœur fondu d'un réacteur à eau pressurisée et le radier en béton du bâtiment réacteur by Mathieu Guillaumé( )

1 edition published in 2008 in French and held by 1 WorldCat member library worldwide

Severe accidents of nuclear power plants are very unlikely to occur, yet it is necessary to be able to predict the evolution of the accident. In some situations, heat generation due to the disintegration of fission products could lead to the melting of the core. If the molten core falls on the floor of the building, it would provoke the melting of the concrete floor. The objective of the studies is to calculate the melting rate of the concrete floor. The work presented in this report is in the continuity of the segregation phase model of Seiler and Froment. It is based on the results of the ARTEMIS experiments. Firstly, we have developed a new model to simulate the transfers within the interfacial area. The new model explains how heat is transmitted to concrete: by conduction, convection and latent heat generation. Secondly, we have modified the coupled modelling of the pool and the interfacial area. We have developed two new models: the first one is the “liquidus model”, whose main hypothesis is that there is no resistance to solute transfer between the pool and the interfacial area. The second one is “the thermal resistance model”, whose main hypothesis is that there is no solute transfer and no dissolution of the interfacial area. The second model is able to predict the evolution of the pool temperature and the melting rate in the tests 3 and 4, with the condition that the obstruction time of the interfacial area is about 105 s. The model is not able to explain precisely the origin of this value. The liquidus model is able to predict correctly the evolution of the pool temperature and the melting rate in the tests 2 and 6
 
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Languages
French (13)

English (5)