Letteratura scientifica selezionata sul tema "Réacteurs à neutrons rapides – Accidents"
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Articoli di riviste sul tema "Réacteurs à neutrons rapides – Accidents":
Natarajan, Rajamani. "Les réacteurs à neutrons rapides en Inde". Revue Générale Nucléaire, n. 6 (novembre 2014): 18–24. http://dx.doi.org/10.1051/rgn/20146018.
Allard, Léonie, e Christophe Poinssot. "Chine : réacteurs à neutrons rapides et nouveaux usages du nucléaire". Revue Générale Nucléaire, n. 5 (settembre 2019): 30–33. http://dx.doi.org/10.1051/rgn/20195030.
Languille, A., P. Millet, S. Pillon e J. Rouault. "Les nouveaux combustibles pour réacteurs à neutrons rapides". Revue Générale Nucléaire, n. 3 (maggio 1997): 47–49. http://dx.doi.org/10.1051/rgn/19973047.
Bouchter, J. C., P. Dufour, J. Guidez, C. Poette, C. Renault e G. Rimpault. "Les réacteurs à neutrons rapides refroidis au gaz". Revue Générale Nucléaire, n. 2 (marzo 2014): 68–76. http://dx.doi.org/10.1051/rgn/20142068.
Billebaud, Annick. "Les nouveaux concepts de réacteurs nucléaires". Reflets de la physique, n. 60 (dicembre 2018): 55–57. http://dx.doi.org/10.1051/refdp/201860055.
Evans, Cécile, Frédéric Laugier, Pierre-Henri Louf, Yolanda Rugama, François Sudreau e Guillaume Vaast. "Avancées sur le multirecyclage en réacteur à eau pressurisée". Revue Générale Nucléaire, n. 1 (2023): 26–33. http://dx.doi.org/10.1051/rgn/20231026.
Lokhov, Alexey. "Le développement de réacteurs rapides au sodium en Russie". Revue Générale Nucléaire, n. 5 (settembre 2019): 34–35. http://dx.doi.org/10.1051/rgn/20195034.
Guidez, J., D. Goux, B. Fontaine e M. Vanier. "Retour d’expérience sur le pilotage des Réacteurs à Neutrons Rapides". Revue Générale Nucléaire, n. 3 (maggio 2007): 42–46. http://dx.doi.org/10.1051/rgn/20073042.
Lacombe, P. "Matériaux utilisés dans les réacteurs à neutrons rapides “super phénix„". Matériaux & Techniques 77, n. 1-2 (1989): 5–12. http://dx.doi.org/10.1051/mattech/198977010005.
Barbe, Alain, Henri Bernard, Claude Boulinier e Lucien Prouteau. "Le développement du cycle du combustible des réacteurs à neutrons rapides". Revue Générale Nucléaire, n. 3 (maggio 1987): 258–62. http://dx.doi.org/10.1051/rgn/19873258.
Tesi sul tema "Réacteurs à neutrons rapides – Accidents":
Lainault, Franck. "Modélisation de la libération d'énergie liée aux accidents graves dans les réacteurs nucléaires à neutrons rapides". Poitiers, 1997. http://www.theses.fr/1997POIT2308.
Andriolo, Lena. "Impact des combustibles sphere-pac innovants sur les performances de sûreté des réacteurs à neutrons rapides refroidis au sodium". Thesis, Université Grenoble Alpes (ComUE), 2015. http://www.theses.fr/2015GREAI067/document.
Future sodium cooled fast reactors (SFRs) have to fulfill the GEN-IV requirements of enhanced safety, minimal waste production, increased proliferation resistance and high economical potential. This PhD project is dedicated to the evaluation of the impact of innovative fuels (especially minor actinides bearing oxide sphere-pac fuels) on the safety performance of advanced SFRs with transmutation option. The SIMMER-III code, originally tailored to mechanistically analyze later phases of core disruptive accidents, is employed for accident simulations. During the PhD project, the code has been extended for a better simulation of the early accident phase introducing the treatment of thermal expansion reactivity effects and for taking into account the specifics of sphere-pac fuels (thermal conductivity and gap conditions). The entire transients (from the initiating event to later accident phases) have been modeled with this extended SIMMER version. Within this PhD work, first the thermo-physical properties of sphere-pac fuel have been modeled and casted into SIMMER-III. Then, a new computational method to account for thermal expansion feedbacks has been developed to improve the initiation phase modeling of the code. The technique has the potential to evaluate these reactivity feedbacks for a fixed Eulerian mesh and in a spatial kinetics framework. At each time step, cell-wise expanded dimensions and densities are calculated based on temperature variations. Density factors are applied to the expanded densities to get an equivalent configuration (in reactivity) with original dimensions and modified densities. New cross sections are calculated with these densities and the reactivity of the equivalent configuration is computed. The developed methods show promising results for uniform and non-uniform expansions. For non-uniform expansions, model improvement needs have been identified and neutronics simulations have been carried out to support future SIMMER extensions. Preliminary results are encouraging. In the third part of the PhD, two core designs with conventional and sphere pac fuels are compared with respect to their transient behavior. These designs were established in the former CP-ESFR project: the working horse core and the optimized CONF2 core (with a large sodium plenum above the core for coolant void worth reduction). The two fuel design options are compared for steady state and transient conditions (Unprotected Loss of Flow accident, ULOF) either at beginning of life (BOL) or under irradiated conditions. Analyses for sphere-pac fuel reveal two main phases to consider at BOL. At start-up, the non-restructured sphere-pac fuel shows a low thermal conductivity compared to pellet fuel of same density. However, the fuel restructures quickly (in a few hours) due to the high thermal gradients and its thermal conductivity recovers. The fuel then shows a behavior close to the pellet one. The study also shows that the CONF2 core leads to a very mild transient for a ULOF accident at BOL. The large upper sodium plenum seems to effectively prevent large positive reactivity insertions. However, stronger reactivity and power peaks are observed under irradiated conditions or when americium is loaded in the core and lower axial blanket. This PhD work demonstrates, under current simulation conditions, that sphere-pac fuels do not seem to cause specific safety issues compared to standard pellet fuels, when loaded in SFRs. The accurate simulation of core thermal expansion reactivity feedbacks by means of the extended SIMMER version plays an important role in the accident timing (simulations confirm the expected delay in the first power peak) and on the energetic potential compared to the case where these feedbacks are omitted. The analyses also confirm the mitigating impact of a large sodium plenum on transients with voiding potential. The behavior of sphere-pac fuel in these conditions opens a perspective to its practical application in SFRs
Mathe, Emmanuel. "Comportement des radiocontaminants dans les confinements d’un réacteur à neutrons rapides refroidi au sodium en situation accidentelle". Electronic Thesis or Diss., Lille 1, 2014. http://www.theses.fr/2014LIL10102.
In the context of the Generation IV initiative, the consequences of a severe-accident (SA) in a sodium-cooled fast reactor must be studied. A SFR (Sodium cooled Fast Reactor) severe accident involves the disruption of the core by super-criticality involving the destruction of a certain number of fuel assemblies. Subsequently the interaction between hot fuel and liquid sodium can lead to a vapor explosion which could create a breach in the primary system. Some contaminated liquid sodium would thus be ejected into the containment building. In this situation, the evaluation of potential releases to the environment (the source term) must forecast the quantity and the chemical speciation of the radiocontaminants likely to be released from the containment building
Mathe, Emmanuel. "Comportement des radiocontaminants dans les confinements d’un réacteur à neutrons rapides refroidi au sodium en situation accidentelle". Thesis, Lille 1, 2014. http://www.theses.fr/2014LIL10102/document.
In the context of the Generation IV initiative, the consequences of a severe-accident (SA) in a sodium-cooled fast reactor must be studied. A SFR (Sodium cooled Fast Reactor) severe accident involves the disruption of the core by super-criticality involving the destruction of a certain number of fuel assemblies. Subsequently the interaction between hot fuel and liquid sodium can lead to a vapor explosion which could create a breach in the primary system. Some contaminated liquid sodium would thus be ejected into the containment building. In this situation, the evaluation of potential releases to the environment (the source term) must forecast the quantity and the chemical speciation of the radiocontaminants likely to be released from the containment building
Guyot, Maxime. "Neutronics and thermal-hydraulics coupling : some contributions toward an improved methodology to simulate the initiating phase of a severe accident in a sodium fast reactor". Thesis, Aix-Marseille, 2014. http://www.theses.fr/2014AIXM4345.
This project is dedicated to the analysis and the quantification of bias corresponding to the computational methodology for simulating the initiating phase of severe accidents on Sodium Fast Reactors. A deterministic approach is carried out to assess the consequences of a severe accident by adopting best estimate design evaluations. An objective of this deterministic approach is to provide guidance to mitigate severe accident developments and recriticalities through the implementation of adequate design measures. These studies are generally based on modern simulation techniques to test and verify a given design. The new approach developed in this project aims to improve the safety assessment of Sodium Fast Reactors by decreasing the bias related to the deterministic analysis of severe accident scenarios.During the initiating phase, the subassembly wrapper tubes keep their mechanical integrity. Material disruption and dispersal is primarily one-dimensional. For this reason, evaluation methodology for the initiating phase relies on a multiple-channel approach. Typically a channel represents an average pin in a subassembly or a group of similar subassemblies. Inthe multiple-channel approach, the core thermal-hydraulics model is composed of 1 or 2 D channels. The thermal-hydraulics model is coupled to a neutronics module to provide an estimate of the reactor power level.In this project, a new computational model has been developed to extend the initiating phase modeling. This new model is based on a multi-physics coupling. This model has been applied to obtain information unavailable up to now in regards to neutronics and thermal-hydraulics models and their coupling
Jadon, Ankita. "Interactions between sodium carbonate aerosols and iodine fission-products". Electronic Thesis or Diss., Université de Lille (2018-2021), 2018. http://www.theses.fr/2018LILUR021.
The safety analysis of Generation IV sodium-cooled fast neutron reactors requires the study of the consequences of a severe accident in case of release into the environment of sodium and the radionuclides it carries (term chemical and radiological source). The global source term therefore depends on both the chemical speciation of sodium aerosols, resulting from the combustion of sodium in the containment, and their interactions with radionuclides. During this thesis, the interactions between sodium carbonate and iodinated gaseous fission products (I2 and HI) were studied at the atomic and macroscopic scales, via a combined theoretical and experimental approach. An analytical expression of the adsorption isotherm has been developed. The relative stability of the sodium carbonate surfaces was determined by ab initio calculations using density functional theory. The reactivity of iodine has been studied for the most stable surfaces and the adsorption isotherms evaluated. In parallel, the kinetics of capture of molecular iodine by sodium carbonate has been determined experimentally for different boundary conditions.The results show an effective capture of the molecular iodine by sodium carbonate at 373 K, varying according to the partial pressure of iodine and the surface of the carbonate sorbent. For the representative conditions of a severe accident, the adsorption sites of the most favorable sodium carbonate surfaces will be mostly bare or doubly occupied depending on the partial pressure of molecular iodine; leading to an equilibrium pressure of less than 2x10-4 bar at 373 K
Singh, Shifali. "Radioscopie X pour les interactions corium-sodium lors d'un scénario d'accident grave". Thesis, Université Paris-Saclay (ComUE), 2019. http://www.theses.fr/2019SACLS114.
In Sodium-cooled Fast Reactors (SFR), hypothetical failure of the core cooling system or the plant protection system may lead to a severe accident scenario. In such a scenario, core materials (fuel and cladding) melt down generating a hot molten mixture called corium. This corium may interact with the coolant (liquid sodium) leading to Fuel Coolant Interaction (FCI) which can generate energetic events and hence jeopardize the reactor structures. The yield of these energetic events strongly depends on the state of the corium-sodium mixture prior to the energetic event. Therefore, the knowledge of the features of the mixture composed of three-phases (i.e., corium, liquid sodium, and sodium vapor) is crucial. The lack of knowledge on the phenomenology of the interaction emphasizes the need to study it with the help of experiments. PLINIUS-2, the future large-mass experimental platform of CEA Cadarache, will be dedicated to experiments aiming at understanding the interaction phenomenology of prototypic corium with coolant (sodium and water). The present research aims to develop a high-energy X-Ray imaging system for this facility, to visualize and better understand the corium-sodium interaction. An image-processing algorithm to analyze the three-phase repartition is also developed to contribute to the improvement of numerical modeling. This Ph.D. research has been executed in three steps. In the first step, a bibliographic study of the past experiments was carried out to better understand the physics of the interaction and the mechanism of fragmentation during corium-sodium interaction. This bibliographic study, along with a statistical analysis of the particle size distribution data of various experiments conducted in the past, revealed that the particles formed in these tests are extremely fine fragments with characteristic diameters smaller than 1 mm. Due to the small particle size and the detection limitations of corium fragments in sodium with our X-Ray system, clouds of particles were detected instead of individual particles. In the second phase, the simulation of clouds of corium particles followed by the designing of phantoms (3D mock-ups) representing the 3-phase medium was carried out. Simulations of clouds of corium fragments in liquid sodium and vapor were performed using the CEA Cadarache in-house tool MODHERATO. Based on the results obtained from the simulations, certain phantoms were designed to conduct some physical experiments. These phantoms representative of the FCI interaction zone were manufactured to experimentally evaluate the performance of the radioscopy system and to facilitate the development and calibration of the image processing software. The third step of this work was dedicated to performing experiments with the phantoms and analyzing the radiographic images by developing an image processing algorithm. Experiments were carried out with phantoms in several configurations with the X-Ray radiography system at the CEA Cadarache KROTOS facility. The radioscopic images obtained were treated by developing a new comprehensive image processing and analysis code called PICSEL to identify the three phases composing the medium. Further verification and validation of the PICSEL software were carried out on a test conducted between corium and water at the KROTOS facility under the Euro-Chinese project “ALISA”. Thus, in this Ph.D. research, an X-Ray imaging system was qualified to visualize the corium-sodium interaction in the future PLINIUS-2-FR facility. A qualitative analysis of the images produced by this system was also performed using the PICSEL software to better characterize the evolution of the three-phase mixture and understand the FCI phenomenon, knowledge of which is deemed essential to improve the safety and designs of future sodium-cooled fast reactors
Lacourcelle, Claire. "Optimisation du procédé de décontamination des composants de réacteurs à neutrons rapides". Aix-Marseille 3, 1994. http://www.theses.fr/1994AIX30065.
Czernecki, Sébastien. "Avancées dans le calcul neutronique des réacteurs à neutrons rapides : démonstration sur le réacteur Super-Phénix". Aix-Marseille 1, 1998. http://www.theses.fr/1998AIX11066.
Rodet, Jean-Claude. "Contribution à l'étude de la turbulence en écoulement moyen tri-dimensionnel : cas des réacteurs nucléaires". Ecully, Ecole centrale de Lyon, 1985. http://www.theses.fr/1985ECDL0012.
Libri sul tema "Réacteurs à neutrons rapides – Accidents":
Friedel, Jacques, Yves Bréchet, François Carré, et et al e Robert Dautray. Fluides Caloporteurs Pour Réacteurs à Neutrons Rapides. EDP Sciences, 2021.
Carré, François, Yves Bréchet, Robert Dautray e Jacques Friedel. Fluides caloporteurs pour réacteurs à neutrons rapides. EDP Sciences, 2020. http://dx.doi.org/10.1051/978-2-7598-2127-3.
Capitoli di libri sul tema "Réacteurs à neutrons rapides – Accidents":
"Chapitre 14. Les réacteurs à neutrons rapides". In Histoire et techniques des réacteurs nucléaires et de leurs combustibles, 523–76. EDP Sciences, 2020. http://dx.doi.org/10.1051/978-2-7598-2032-0-018.
"Chapitre 14. Les réacteurs à neutrons rapides". In Histoire et techniques des réacteurs nucléaires et de leurs combustibles, 523–76. EDP Sciences, 2020. http://dx.doi.org/10.1051/978-2-7598-2032-0.c018.
"Frontmatter". In Fluides caloporteurs pour réacteurs à neutrons rapides, i—iv. EDP Sciences, 2020. http://dx.doi.org/10.1051/978-2-7598-2127-3-fm.
Friedel, Jacques. "Préface". In Fluides caloporteurs pour réacteurs à neutrons rapides, ix—x. EDP Sciences, 2020. http://dx.doi.org/10.1051/978-2-7598-2127-3-001.
"Table des matières". In Fluides caloporteurs pour réacteurs à neutrons rapides, v—viii. EDP Sciences, 2020. http://dx.doi.org/10.1051/978-2-7598-2127-3-toc.
Carré, Frank. "Chapitre 2 Les fluides caloporteurs dans les différentes options de la génération IV : le retour d’expérience". In Fluides caloporteurs pour réacteurs à neutrons rapides, 43–62. EDP Sciences, 2020. http://dx.doi.org/10.1051/978-2-7598-2127-3-003.
Gauché, François. "Chapitre 3 Le cahier des charges des réacteurs à neutrons rapides du futur". In Fluides caloporteurs pour réacteurs à neutrons rapides, 63–78. EDP Sciences, 2020. http://dx.doi.org/10.1051/978-2-7598-2127-3-004.
Bamberger, Yves. "Chapitre 4 Les conclusions du séminaire : quelles actions en termes de recherche et développement ?" In Fluides caloporteurs pour réacteurs à neutrons rapides, 79–88. EDP Sciences, 2020. http://dx.doi.org/10.1051/978-2-7598-2127-3-005.
Brézin, Édouard. "Postface". In Fluides caloporteurs pour réacteurs à neutrons rapides, 89–91. EDP Sciences, 2020. http://dx.doi.org/10.1051/978-2-7598-2127-3-006.
Bréchet, Yves, Robert Dautray e Jacques Friedel. "Chapitre 1 Introduction sur les fluides caloporteurs pour les réacteurs à neutrons rapides, une vue générale des problèmes scientifiques et techniques". In Fluides caloporteurs pour réacteurs à neutrons rapides, 11–42. EDP Sciences, 2020. http://dx.doi.org/10.1051/978-2-7598-2127-3-002.