Oxygen segregation in pre-hydrided Zircaloy-4 cladding during a simulated LOCA transient
| Autor: | S. Guilbert, Antoine Ambard, Marie-Christine Baietto, Martine Blat, Jean Desquines, Elodie Torres, Michel Coret, Pauline Lacote |
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| Přispěvatelé: | Institut de Radioprotection et de Sûreté Nucléaire (IRSN), Mécanique Multiéchelle pour les solides (MIMESIS), Laboratoire de Mécanique des Contacts et des Structures [Villeurbanne] (LaMCoS), Institut National des Sciences Appliquées de Lyon (INSA Lyon), Institut National des Sciences Appliquées (INSA)-Université de Lyon-Institut National des Sciences Appliquées (INSA)-Université de Lyon-Centre National de la Recherche Scientifique (CNRS)-Institut National des Sciences Appliquées de Lyon (INSA Lyon), Institut National des Sciences Appliquées (INSA)-Université de Lyon-Institut National des Sciences Appliquées (INSA)-Université de Lyon-Centre National de la Recherche Scientifique (CNRS), Institut de Recherche en Génie Civil et Mécanique (GeM), Université de Nantes - UFR des Sciences et des Techniques (UN UFR ST), Université de Nantes (UN)-Université de Nantes (UN)-École Centrale de Nantes (ECN)-Centre National de la Recherche Scientifique (CNRS), EDF R&D (EDF R&D), EDF (EDF) |
| Jazyk: | angličtina |
| Rok vydání: | 2017 |
| Předmět: |
Zirconium
Materials science Hydrogen Zirconium alloy chemistry.chemical_element Thermodynamics 02 engineering and technology Atmospheric temperature range 021001 nanoscience & nanotechnology Cladding (fiber optics) 7. Clean energy Oxygen lcsh:TK9001-9401 [SPI]Engineering Sciences [physics] 020303 mechanical engineering & transports 0203 mechanical engineering chemistry Phase (matter) lcsh:Nuclear engineering. Atomic power 0210 nano-technology Loss-of-coolant accident |
| Zdroj: | EPJ N-Nuclear Sciences & Technologies EPJ N-Nuclear Sciences & Technologies, EDP Sciences, 2017, 3, ⟨10.1051/epjn/2017020⟩ EPJ Nuclear Sciences & Technologies, Vol 3, p 27 (2017) |
| ISSN: | 2491-9292 |
| DOI: | 10.1051/epjn/2017020⟩ |
| Popis: | International audience; Oxygen and hydrogen distributions are key elements influencing the residual ductility of zirconium-based nuclear fuel cladding during the quench phase following a Loss Of Coolant Accident (LOCA). During the high temperature oxidation, a complex partitioning of the alloying elements is observed. A finite-difference code for solving the oxygen diffusion equations has been developed by Institut de Radioprotection et de Surete Nucleaire to predict the oxygen profile within the samples. The comparison between the calculations and the experimental results in the mixed alpha+beta region shows that the oxygen diffusion is not accurately predicted by the existing modeling. This work aims at determining the key parameters controlling the average oxygen profile within the sample in the two-phase regions at 1200 degrees C. High temperature steam oxidation tests interrupted by water quench were performed using pre-hydrided Zircaloy-4 samples. Experimental oxygen distribution was measured by Electron Probe Micro-Analysis (EPMA). The phase distributions within the cladding thickness, was measured using image analysis to determine the radial profile of alpha(O) phase fraction. It is further demonstrated and experimentally checked that the alpha-phase fraction in these regions follows a diffusion-like radial profile. A new phase fraction modeling is then proposed in the cladding metallic part during steam oxidation. The modeling results are compared to a large set of experiments including the influence of exposure duration and hydrogen content. Another key outcome from this modeling is that oxygen average profile is straightforward derived from the proposed modeling. |
| Databáze: | OpenAIRE |
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