TY - JOUR
T1 - Investigation of the microstructure of He+ ion-irradiated TiBe12 and CrBe12 using ex-situ transmission electron microscopy
AU - Sharp, Jo
AU - Kuksenko, Viacheslav
AU - Gaisin, Ramil
AU - Greaves, Graeme
AU - Hinks, Jonathan
AU - Vladimirov, Pavel
AU - Donnelly, Steve
N1 - Funding Information:
This work has been carried out within the framework of the EUROfusion Consortium, funded by the European Union via the Euratom Research and Training Programme (Grant Agreement No 101052200 — EUROfusion). Views and opinions expressed are however those of the author(s) only and do not necessarily reflect those of the European Union or the European Commission. Neither the European Union nor the European Commission can be held responsible for them.
Funding Information:
This project was funded by the Engineering and Physical Sciences Research Council, United Kingdom (EPSRC) under grant number EP/T027193/1 . The construction of MIAMI–2 was funded by EPSRC grant number EP/M028283/1 . Sample preparation was carried out at UKAEA's Materials Research Facility, which has been funded by and is part of the UK's National Nuclear User Facility and Henry Royce Institute for Advanced Materials and the RCUK Energy Programme (grant number EP/T012250/1 ). This work has been part-funded by the EPSRC Energy Programme (grant number EP/W006839/1).
Publisher Copyright:
© 2023
PY - 2024/1/1
Y1 - 2024/1/1
N2 - Titanium and chromium beryllides, TiBe
12 and CrBe
12, are materials of potential future importance as neutron multipliers for tritium breeding in nuclear fusion reactors. Beryllium experiences extremely high transmutation according to a n →2n transmutation reaction in which both tritium and helium are produced, which normally form bubbles in solids at the relevant concentration range. Neutron irradiation from the fusion plasma also introduces point defects into solids. The ensuing effect of this environment on the beryllides’ microstructure is poorly characterised, but important for understanding beryllides’ mechanical properties and their evolution in the irradiative environment inside a fusion reactor. This study is intended to initially determine and describe the microstructural features that occur in TiBe
12 and CrBe
12 when He and fast-particle-induced point defects have been introduced at fusion reactor neutron breeder relevant temperatures. In this study, beryllide samples were implanted with 300 kV He at a range of temperatures between 387 and 900 °C, sectioned down through the implantation surface with a focused ion beam post-irradiation, and the resulting microstructures examined using transmission electron microscopy, electron-dispersive X-ray spectroscopy (EDX/EDS) and precession diffraction mapping. Nanometre-scale bubbles grew in both TiBe
12 and CrBe
12 at 600 °C and larger (100+ nm) bubbles, some faceted, grew at 900 °C. Some bubbles in CrBe
12 were lined with Cr, with some of the Cr oxidised. TiBe
12 developed planar faults, on {110} planes at 600 °C and below but on to {111} at 900 °C. Faults were preferentially associated with large bubbles. The displacement vectors of faults on the {110} planes had some commonality with previous studies that found displacement vectors of the two types R=[Formula presented]〈110〉; the present study also found faults that did not match either previously found type. CrBe
12 also developed planar faults but the appearance of these was quite different from the typical striped appearance of planar stacking faults and their nature remains unknown. Oxide particles from manufacture were found in both beryllides, most prominently in CrBe
12.
AB - Titanium and chromium beryllides, TiBe
12 and CrBe
12, are materials of potential future importance as neutron multipliers for tritium breeding in nuclear fusion reactors. Beryllium experiences extremely high transmutation according to a n →2n transmutation reaction in which both tritium and helium are produced, which normally form bubbles in solids at the relevant concentration range. Neutron irradiation from the fusion plasma also introduces point defects into solids. The ensuing effect of this environment on the beryllides’ microstructure is poorly characterised, but important for understanding beryllides’ mechanical properties and their evolution in the irradiative environment inside a fusion reactor. This study is intended to initially determine and describe the microstructural features that occur in TiBe
12 and CrBe
12 when He and fast-particle-induced point defects have been introduced at fusion reactor neutron breeder relevant temperatures. In this study, beryllide samples were implanted with 300 kV He at a range of temperatures between 387 and 900 °C, sectioned down through the implantation surface with a focused ion beam post-irradiation, and the resulting microstructures examined using transmission electron microscopy, electron-dispersive X-ray spectroscopy (EDX/EDS) and precession diffraction mapping. Nanometre-scale bubbles grew in both TiBe
12 and CrBe
12 at 600 °C and larger (100+ nm) bubbles, some faceted, grew at 900 °C. Some bubbles in CrBe
12 were lined with Cr, with some of the Cr oxidised. TiBe
12 developed planar faults, on {110} planes at 600 °C and below but on to {111} at 900 °C. Faults were preferentially associated with large bubbles. The displacement vectors of faults on the {110} planes had some commonality with previous studies that found displacement vectors of the two types R=[Formula presented]〈110〉; the present study also found faults that did not match either previously found type. CrBe
12 also developed planar faults but the appearance of these was quite different from the typical striped appearance of planar stacking faults and their nature remains unknown. Oxide particles from manufacture were found in both beryllides, most prominently in CrBe
12.
KW - Beryllides
KW - Helium ion irradiation
KW - Faults
KW - Defects
KW - Bubbles
UR - http://www.scopus.com/inward/record.url?scp=85177185549&partnerID=8YFLogxK
U2 - 10.1016/j.jnucmat.2023.154812
DO - 10.1016/j.jnucmat.2023.154812
M3 - Article
VL - 588
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
SN - 0022-3115
M1 - 154812
ER -