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首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >Microstructural examination of neutron, proton and self-ion irradiation damage in a model Fe9Cr alloy
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Microstructural examination of neutron, proton and self-ion irradiation damage in a model Fe9Cr alloy

机译：模型Fe9Cr合金中子，质子和自离子照射损伤的微观结构检查

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Transmission electron microscopy (TEM) was used to compare the microstructural defects produced in an Fe9Cr model alloy during exposure to neutrons, protons, or self-ions. Samples from the same model alloy were irradiated using fission-neutrons, 2 MeV Fe+ ions or 1.2 MeV protons at similar temperatures (similar to 300 degrees C) and similar doses (similar to 2.0 dpa). The neutron-irradiated alloy contained visible interstitial dislocation loops with b = 111, and on average similar to 5 nm in size. The density varied from 2 +/- 1 x 10(20) m(-3) (in the matrix far from dislocations and boundaries) to 1.2 +/- 0.3 x10(23) m(-3) (close to helical dislocation lines). Chromium alpha'-phase precipitates were also identified at a density of 7.4 +/- 0.4 x10(23) m(-3). Self-ion irradiation produced mostly homogeneously distributed dislocation loops (6-7 nm on average), and with a greater fraction of 100 loops (similar to 40%) than was seen in the neutron-irradiated alloy, and at a density of 6.8 +/- 0.8 x10(22) m(-3). In contrast to the loops produced by neutron irradiation, the self-ion irradiated Fe9Cr contained only vacancy-type loops. Chromium also remained in solution. Proton-irradiated Fe9Cr contained interstitial dislocation loops close to helical-dislocation segments, similar to the neutronirradiated sample. Chromium alpha'-phases were also identified in the proton-irradiated sample at a density of 2.5 +/- 0.3 x 10(23) m(-3), and large voids (up to 7 nm) were found at a density over 10(22)m(-3). Like the neutron-irradiated sample, the density of dislocation loops was also heterogeneously distributed; far from grain boundaries and dislocation lines the density was 2.5 +/- 0.4 x10(22) m(-3), while close to helical dislocation lines the density was 8.1 +/- 1.3 x10(22) m(-3). (c) 2020 Elsevier B.V. All rights reserved.
机译：透射电子显微镜（TEM）用于比较在暴露于中子，质子或自离子期间FE9CR模型合金中产生的微观结构缺陷。使用裂变 - 中子，2meV Fe +离子或1.2MeV质子在类似温度（类似于300℃）和类似剂量（类似于2.0dPa）的情况下，照射来自相同模型合金的样品。中子辐照合金含有B = 111的可见间质脱位环，平均值与5nm的大小相似。密度从2 +/- 1×10（20）m（-3）（在远离脱位和边界的基质中）变化至1.2 +/- 0.3 x10（23）m（-3）（靠近螺旋错位线）。还以7.4 +/- 0.4×10（23）m（-3）的密度鉴定铬α-相沉淀物。自离子照射主要产生均匀分布的位错环（平均6-7nm），并且具有比中子辐照合金在中子辐照合金中观察到的100个环（类似于40％），并且密度为6.8 + / - 0.8 x10（22）m（-3）。与中子辐射产生的环相比，自离子照射Fe9cr仅包含空位型环。铬还留在溶液中。质子辐照的Fe9cr含有靠近螺旋脱位段的间隙位错环，类似于中毒辐射的样品。在质子辐照的样品中也以2.5 +/- 0.3×10（23）m（-3）的密度在质子辐射的样品中鉴定出铬α-相，并且在10升的密度下发现大空隙（最多7nm） （22）m（-3）。与中子辐照样品一样，位错环的密度也是异质分布的;远离谷物边界和脱位线密度为2.5 +/- 0.4 x10（22）m（-3），而密度为8.1 +/- 1.3 x10（22）m（-3）的螺旋脱位线。 （c）2020 Elsevier B.v.保留所有权利。

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