| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
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| Symposium
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Special Topics in Nuclear Materials: Lessons Learned; Non-Energy Systems; and Coupled Extremes
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| Presentation Title |
The Recovery of Irradiation Damage for Zircaloy-2 and Zircaloy-4 following Irradiation at Higher Temperatures of 377-410°C |
| Author(s) |
Brian V. Cockeram, Bruce Kammenzind |
| On-Site Speaker (Planned) |
Brian V. Cockeram |
| Abstract Scope |
Zircaloy-2 and Zircaloy-4 irradiated at temperatures between nominally 377°C to 421°C in the ATR exhibited a coarser distribution of loops that results in about 10%-60% less irradiation hardening than reported in the literature for irradiations at 260-326°C. Irradiation at lower flux results in greater amorphization of precipitates that are shown to result in a finer loop size distribution and higher irradiation hardening and differences in recovery kinetics. Post-irradiation annealing at 343-427°C produced an increase in irradiation hardening in the first 1-10 hours of annealing. This Radiation Anneal Hardening (RAH) was followed by slower recovery than observed for irradiations at 260-326°C. Faster recovery with no RAH was observed for annealing at temperatures of 454-510°C, which is about 50°C above the irradiation temperature. This suggests the annealing temperature needs to be about 25-50°C higher than the irradiation temperature in order for vacancy emission from defects and vacancy mobility to produce recovery. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Mechanical Properties, Characterization |