TEM characterisation of heavy-ion irradiation damage in FeCr alloys

Xu, Shuo; Yao, Zhongwen; Jenkins, M. L.

doi:10.1016/j.jnucmat.2008.12.078

Cited by 45 publications

(29 citation statements)

References 12 publications

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“…In our own recent experiments in Fe irradiated in the bulk with 0.5-3 MeV Fe + ions to ~ 10 dpa at 500 o C, we also found almost exclusively interstitial <100> loops, whilst at 300 o C a mixture of <100> and ½<111> loops was present. In FeCr alloys, however, both loop types were present at 500 o C [15]. In these and other experiments there does seem a clear pattern for <100> loops to predominate in pure Fe at irradiation temperatures T irr ≥ 400 o C. In contrast, in Fe irradiated at 60 o C with neutrons, only ½<111> loops were identified, again of interstitial nature [16].…”

Section: Discussionmentioning

confidence: 50%

The temperature dependence of heavy-ion damage in iron: A microstructural transition at elevated temperatures

Yao

Jenkins

Hernández‐Mayoral

et al. 2010

Philosophical Magazine

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158

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Section: Discussionmentioning

confidence: 50%

The temperature dependence of heavy-ion damage in iron: A microstructural transition at elevated temperatures

Yao

Jenkins

Hernández‐Mayoral

et al. 2010

Philosophical Magazine

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158

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“…: b ! analysis based on the method used by Yao et al [27,28]. Indeed, unlike samples irradiated as thin foils, where some dislocation loops with Burgers vectors normal to the free surfaces escape to them [29], we can assume that the Burgers vectors are equiprobable amongst a given family (i.e.…”

Section: Methodsmentioning

confidence: 99%

Microstructural characterization of Eurofer-97 and Eurofer-ODS steels before and after multi-beam ion irradiations at JANNUS Saclay facility

Brimbal

Beck

Troeber

et al. 2015

Journal of Nuclear Materials

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a b s t r a c t RAFM steels such as Eurofer-97 and Eurofer-ODS are potential structural materials for future fusion reactors. In order to study their resistance to the high energy neutrons they will be subjected to in this context, we have irradiated these materials in single-, dual-and triple-beam mode to 26 dpa at 400 C. In single-beam mode (Fe ions only), both materials resist swelling but dislocation loops form. For dual-(Fe and He ions) and triple-beam (Fe, He and H) modes, the same dislocation loop microstructure is observed as for the single-beam mode, but small cavities form, aided by the presence of gases. Despite the formation of cavities, swelling is very low for the present conditions. The influence of ODS particles on swelling is briefly discussed.

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“…For these reasons, there has been much recent work on using self ion irradiation in various materials and particularly Fe-based alloys to mimic the damage caused by fast neutrons [27][28][29]. This has the advantage of producing samples which are not radioactive and high levels of damage can be built up in relatively short time periods.…”

Section: Introductionmentioning

confidence: 99%

“…Typically TEM has been used to study the dislocation structures produced by irradiation [29,30], while atom probe tomography (APT) has been used to study the changes in local chemistry [17,31,32]. As the damaged layers are shallow, traditional bulk mechanical tests cannot be used to study the mechanical properties; however nanoindentation has recently been used to test the hardness of these layers, as compared to bulk materials [27,28,[33][34][35].…”

Section: Introductionmentioning

confidence: 99%