Development of radiation damage during in-situ Kr++ irradiation of FeNiCr model austenitic steels
| Autor: | Arthur T. Motta, M. Desormeaux, Caroline Bisor, Marquis A. Kirk, B. Rouxel, Alexandre Legris, Y. de Carlan |
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| Přispěvatelé: | CEA-Direction de l'Energie Nucléaire (CEA-DEN), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Unité Matériaux et Transformations - UMR 8207 (UMET), Centre National de la Recherche Scientifique (CNRS)-Université de Lille-Ecole Nationale Supérieure de Chimie de Lille (ENSCL)-Institut National de la Recherche Agronomique (INRA), CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire) (CEA-DES (ex-DEN)), Institut de Chimie du CNRS (INC)-Institut National de la Recherche Agronomique (INRA)-Centre National de la Recherche Scientifique (CNRS)-Université de Lille-Ecole Nationale Supérieure de Chimie de Lille (ENSCL), Institut National de la Recherche Agronomique (INRA)-Ecole Nationale Supérieure de Chimie de Lille (ENSCL)-Institut de Chimie du CNRS (INC)-Université de Lille-Centre National de la Recherche Scientifique (CNRS), Institut National de la Recherche Agronomique (INRA)-Ecole Nationale Supérieure de Chimie de Lille (ENSCL)-Université de Lille-Centre National de la Recherche Scientifique (CNRS) |
| Rok vydání: | 2016 |
| Předmět: |
Cladding (metalworking)
Nuclear and High Energy Physics Materials science chemistry.chemical_element 02 engineering and technology 01 natural sciences Materials Science(all) 0103 physical sciences medicine Radiation damage [CHIM]Chemical Sciences General Materials Science Irradiation ComputingMilieux_MISCELLANEOUS 010302 applied physics Austenite Metallurgy 021001 nanoscience & nanotechnology Microstructure Surface coating Nickel chemistry Nuclear Energy and Engineering Swelling medicine.symptom 0210 nano-technology |
| Zdroj: | Journal of Nuclear Materials Journal of Nuclear Materials, Elsevier, 2016, 475, pp.156-167. ⟨10.1016/j.jnucmat.2016.04.012⟩ Journal of Nuclear Materials, 2016, 475, pp.156-167. ⟨10.1016/j.jnucmat.2016.04.012⟩ |
| ISSN: | 0022-3115 |
| DOI: | 10.1016/j.jnucmat.2016.04.012 |
| Popis: | In situ irradiations of 15Cr/15Ni Ti and 15Cr/25Ni Ti model austenitic steels were performed at the Intermediate Voltage Electron Microscope (IVEM)-Tandem user Facility (Argonne National Laboratory) at 600 °C using 1 MeV Kr++. The experiment was designed in the framework of cladding development for the GEN IV Sodium Fast Reactors (SFR). It is an extension of previous high dose irradiations on those model alloys at JANNuS-Saclay facility in France, aimed at investigating swelling mechanisms and microstructure evolution of these alloys under irradiation [1]. These studies showed a strong influence of Ni in decreasing swelling. In situ irradiations were used to continuously follow the microstructure evolution during irradiation using both diffraction contrast imaging and recording of diffraction patterns. Defect analysis, including defect size, density and nature, was performed to characterize the evolving microstructure and the swelling. Comparison of 15Cr/15Ni Ti and 15Cr/25Ni Ti irradiated microstructure has lent insight into the effect of nickel content in the development of radiation damage caused by heavy ion irradiation. The results are quantified and discussed in this paper. |
| Databáze: | OpenAIRE |
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