Microstructural analysis of an HT9 fuel assembly duct irradiated in FFTF to 155 dpa at 443 °C
Microstructural analysis of an HT9 fuel assembly duct irradiated in FFTF to 155 dpa at 443 °C
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HT9 燃料组件管道在 443 °C 下经 FFTF 辐照至 155 dpa 的微观结构分析
DOI:
10.1016/j.jnucmat.2009.06.010
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发表时间:
2009
影响因子:
3.1
通讯作者:
F. Garner
中科院分区:
文献类型:
--
作者:
B. H. Sencer;J. Kennedy;J. Cole;S. Maloy;F. Garner
The majority of data on the irradiation response of ferritic/martensitic steels has been derived from simple free-standing specimens irradiated in experimental assemblies under well-defined and near-constant conditions, while components of long-lived fuel assemblies are more complex in shape and will experience progressive changes in environmental conditions. To explore whether the resistance of HT9 to void swelling is maintained under more realistic operating conditions, the radiation-induced microstructure of an HT9 ferritic/martensitic hexagonal duct was examined following a six-year irradiation of a fuel assembly in the Fast Flux Test Reactor Facility (FFTF). The calculated irradiation exposure and average operating temperature of the duct at the location examined were ∼155dpa at ∼443°C. It was found that dislocation networks were predominantly composed of (a/2)<111> Burgers vectors. Surprisingly, for such a large irradiation dose, type a<100> interstitial loops were observed. Additionally, a high density of precipitation occurred. These two microstructural characteristics may have contributed to the rather low swelling level of 0.3%.