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AbstractAbstract
[en] The extreme operating conditions envisaged for the fuel cladding of generation IV reactors (high temperature: 400 C-700 C, and high dose of irradiation: up to 150 dpa) require the development of new materials. Ferritic/martensitic steels reinforced by a dispersion of nanometric oxides (ODS: Oxide Dispersion Strengthened) are now one of the options for fissile cladding materials dedicated to the high combustion rates of a SFR. In fact, these steels exhibit a good resistance to swelling for high doses, up to 150 dpa, and a good resistance to creep deformation at high temperature thanks to the presence of nanometric oxides. However, neutron irradiation induces microchemical changes in the structure of these materials such as the separation of α-α' phases and Cr depletion at the grain boundaries. These microstructural modifications can considerably affect the mechanical properties of these steels and could notably degrade the resistance to creep deformation and the resistance to swelling. These phenomena have been relatively little studied in ODS steels, in particular the precipitation of the α' phase and its impact on the hardening of materials. Thus, the objective of the thesis work is to study the phenomenon of separation of the α-α'phases as well as the behavior of grain boundaries under thermal aging, under ion irradiation and also under neutron irradiation. Excluding irradiation, the results obtained show that the precipitate α' is formed by a non classical mechanism in ODS steels after thermal aging. It has been found that the oxide nano-reinforcements serve as a heterogeneous germination site for α''phases, thus accelerating the later's growth kinetics. If these phases initially harden the material significantly, their hardening effect is dependent on their kinetics of precipitation. In addition to the formation of these Cr-rich phases, Cr segregation at the grain boundaries has been demonstrated. It has been shown that enrichment in Cr is strongly dependent on the disorientation of the grain boundary and could, in the case of highly disoriented joints, cause a spinodal decomposition localized at the grain boundary. Under ion irradiation, it has been shown that the defects generate an induced Cr segregation depleting the grain boundaries, in particular in the case of an ODS Fe-14Cr alloy. α'-isolated droplets are 6 observed in the case of Fe-18Cr ODS while a mechanism of spinodal decomposition induced under irradiation has been observed in the case of Fe-14Cr ODS. The mechanisms highlighted in thermal ageing and under ion irradiation made it possible to understand the microstructures observed after neutron irradiation. (author)
[fr]
Les conditions extremes de fonctionnement envisagees pour le gainage combustible des reacteurs de 4 eme generation (temperature elevee: 400 C-700 C, et forte dose d'irradiation: jusqu'a 150 deplacements par atome (dpa)) necessitent de developper de nouveaux materiaux. Les aciers ferritiques/martensitiques renforces par une dispersion d'oxydes nanometriques (ODS: Oxide Dispersion Strengthened) constituent aujourd'hui l'une des options pour les materiaux de gainage fissile dedie aux forts taux de combustion d'un RNRNa. En effet, ces aciers presentent une bonne resistance au gonflement pour de fortes doses, allant jusqu'a 150 dpa, et une bonne tenue a la deformation en fluage a haute temperature grace aux renforts d'oxydes nanometriques. Cependant, l'irradiation neutronique induit des modifications microchimiques dans la structure de ces materiaux telles que la demixtion de phases α-α' et la depletion en Cr aux joints de grains. Ces modifications microstructurales peuvent impacter considerablement les proprietes mecaniques de ces aciers et pourraient degrader notamment la resistance a la deformation en fluage et la resistance au gonflement. Ces phenomenes ont ete relativement peu etudies dans les aciers ODS, en particulier la precipitation de la phase α' et son impact sur le durcissement des materiaux. Ainsi, l'objectif des travaux de these est d'etudier le phenomene de demixtion des phases α-α' ainsi que le comportement des joints de grains sous vieillissement thermique, sous irradiation ionique et egalement sous irradiation aux neutrons. Hors irradiation, les resultats obtenus montrent que la phase α' se forme par un mecanisme non classique dans les aciers ODS apres vieillissement thermique. Il a ete constate que les nano-renforts d'oxydes servent de site de germination heterogene pour la phase α', accelerant ainsi la cinetique de croissance de cette derniere. Si dans un premier temps ces phases durcissent significativement le materiau, leur effet durcissant diminue au fur et a mesure de leur croissance. En plus de la formation de ces phases riches en Cr, une segregation de Cr aux joints de grains a ete mise en evidence. Il a ete montre que l'enrichissement en Cr etait fortement dependant de la desorientation du joint et pouvait, dans le cas des joints fortement desorientes, engendrer une decomposition spinodale localisee au joint de grains. Sous irradiation aux ions, il a ete montre que les flux de defauts engendraient une segregation induite de Cr appauvrissant les joints de grains. Dans le cas de l'alliage Fe-18Cr ODS, la phase α' est apparu sous irradiation sous forme de precipites isoles alors que dans le cas de l'alliage ODS Fe-14Cr, il a ete constate un mecanisme de decomposition spinodale induite sous irradiation. Les mecanismes mis en evidence en recuit thermique et sous 5 irradiation aux ions ont permis de comprendre les microstructures observees apres irradiation aux neutrons.Original Title
Comportement sous irradiation des aciers ODS (Oxide Dispersion Strengthened) pour le gainage combustible des reacteurs de 4eme generation
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3 Jul 2020; 235 p; 169 refs.; Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addresses; Science des Materiaux
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