Damage tolerance of nuclear graphite at elevated temperatures.
Damage tolerance of nuclear graphite at elevated temperatures.
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DOI:
10.1038/ncomms15942
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发表时间:
2017-06-30
影响因子:
16.6
通讯作者:
Ritchie RO
中科院分区:
文献类型:
--
作者:
Liu D;Gludovatz B;Barnard HS;Kuball M;Ritchie RO
Nuclear-grade graphite is a critically important high-temperature structural material for current and potentially next generation of fission reactors worldwide. It is imperative to understand its damage-tolerant behaviour and to discern the mechanisms of damage evolution under in-service conditions. Here we perform in situ mechanical testing with synchrotron X-ray computed micro-tomography at temperatures between ambient and 1,000 °C on a nuclear-grade Gilsocarbon graphite. We find that both the strength and fracture toughness of this graphite are improved at elevated temperature. Whereas this behaviour is consistent with observations of the closure of microcracks formed parallel to the covalent-sp2-bonded graphene layers at higher temperatures, which accommodate the more than tenfold larger thermal expansion perpendicular to these layers, we attribute the elevation in strength and toughness primarily to changes in the residual stress state at 800–1,000 °C, specifically to the reduction in significant levels of residual tensile stresses in the graphite that are ‘frozen-in’ following processing. Nuclear-grade graphite is an important high-temperature structural material for fission reactors. Here, the authors perform simultaneous X-ray tomography and mechanical testing on a nuclear-grade graphite, finding simultaneous improvement of strength and toughness at elevated temperatures which they attribute primarily to reduction of residual tensile stresses in the as-made material.