Heavy ion irradiation induced dislocation loops in AREVA's M5 alloy
Cover letter for the second revised submission of the article to the Journal of Nuclear MaterialsPressurized water reactor (PWR) Zr-based alloy structural materials show creep and growth under neutron irradiation as a consequence of the irradiation induced microstructural changes in the alloy. A better scientific understanding of these microstructural processes can improve simulation programs for structural component deformation and simplify the development of advanced deformation resistant alloys. As in-pile irradiation leads to high material activation and requires long irradiation times, the objective of this work was to study whether ion irradiation is an applicable method to simulate typical PWR neutron damage in Zr-based alloys, with AREVA's M5 ® alloy as reference material. The irradiated specimens were studied by electron backscatter diffraction (EBSD), positron Doppler broadening spectroscopy (DBS) and in-situ transmission electron microscopy (TEM) at different dose levels and temperatures. The irradiation induced microstructure consisted of -and
The performance of Zr1NbSnFe alloys within the range of Sn 0–0.65 % and Fe 0.03–0.35 % were studied through irradiation of fuel rods in two pressurized water reactors (PWRs) operating with significantly different fuel management strategies. Material test rod irradiations have also been launched in order to determine irradiation growth and corrosion behaviour on tubes irradiated under conditions representative of guide tubes. Results show that the increase in tin content up to 0.3 % does not significantly change the corrosion resistance nor the hydrogen pick-up compared to Zr1Nb alloy, while ensuring a higher creep resistance and an improved dimensional stability. On the contrary, at 0.5 % Sn, the corrosion resistance can be significantly degraded under demanding conditions. The iron addition to the alloy can be considered as a second order parameter for both corrosion and creep properties.
No abstract
The performance of Zr1NbSnFe alloys within the range of Sn 0–0.65 % and Fe 0.03–0.35 % were studied through irradiation of fuel rods in two pressurized water reactors (PWRs) operating with significantly different fuel management strategies. Material test rod irradiations have also been launched in order to determine irradiation growth and corrosion behaviour on tubes irradiated under conditions representative of guide tubes. Results show that the increase in tin content up to 0.3 % does not significantly change the corrosion resistance nor the hydrogen pick-up compared to Zr1Nb alloy, while ensuring a higher creep resistance and an improved dimensional stability. On the contrary, at 0.5 % Sn, the corrosion resistance can be significantly degraded under demanding conditions. The iron addition to the alloy can be considered as a second order parameter for both corrosion and creep properties.
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