Helium induced microstructure damage, nano-scale grain formation and helium retention behaviour of ZrC

S Agarwal, A Bhattacharya, P Trocellier, SJ Zinkle - Acta Materialia, 2019 - Elsevier
Transition-metal ultra-high temperature ceramics are promising materials for nuclear
structural applications. However, an understanding of their response to high-temperature …

Ion irradiation and radiation effect characterization at the JANNUS-Saclay triple beam facility

L Beck, Y Serruys, S Miro, P Trocellier… - Journal of Materials …, 2015 - cambridge.org
JANNUS (Joint Accelerators for Nanosciences and Nuclear Simulation), the unique triple
beam facility in Europe, offers the possibility to produce three ion beams simultaneously for …

Raman investigation of ion irradiated TiC and ZrC

S Pellegrino, P Trocellier, L Thomé, S Miro… - Nuclear Instruments and …, 2019 - Elsevier
Single crystals of transition metal carbides from group IV, TiC 1-x and ZrC 1-x, have been
irradiated at room temperature (RT) with 1.2 MeV gold ions for various fluences in the range …

Effects of helium irradiation on fine grained β-SiC synthesized by spark plasma sintering

S Gavarini, J Baillet, N Millard-Pinard, V Garnier… - Journal of the European …, 2020 - Elsevier
Silicon carbide has a high resistance to irradiation making it a material of choice for use in
the nuclear reactors. In this work, we focus on experiments involving implantation of 30 keV …

ERDA, RBS, TEM and SEM characterization of microstructural evolution in helium-implanted Hastelloy N alloy

J Gao, L Bao, H Huang, Y Li, Q Lei, Q Deng… - Nuclear Instruments and …, 2017 - Elsevier
Hastelloy N alloy was implanted with 30 keV, 5× 10 16 ions/cm 2 helium ions at room
temperature, and subsequent annealed at 600° C for 1 h and further annealed at 850° C for …

Helium assisted migration of silver implanted into SiC

TT Hlatshwayo, CE Maepa, M Msimanga, M Mlambo… - Vacuum, 2021 - Elsevier
The effects of helium (He) in the migration behaviour of silver (Ag) implanted into
polycrystalline siclicon carbide (SiC) was investigated. Polycrystalline SiC wafers were first …

Characterisation of ODS Fe-14Cr-2W-0.3 Ti before and after high temperature triple and low temperature single ion irradiations

M Šćepanović, T Leguey, MA Auger… - Materials …, 2018 - Elsevier
Oxide dispersion strengthened reduced activation ferritic steels are being considered as
structural materials for future fusion reactors and Gen IV fission reactors. In this work, the …

Effects of single-and simultaneous triple-ion-beam irradiation on an oxide dispersion-strengthened Fe12Cr steel

V de Castro, S Lozano-Perez, M Briceno… - Journal of Materials …, 2015 - Springer
Oxide dispersion-strengthened (ODS) steels are main candidates for structural applications
in future fusion reactors. Understanding their irradiation-induced behaviour is a key in …

Non-classical applications of chemical analysis based on nuclear activation

M Grdeń - Journal of Radioanalytical and Nuclear Chemistry, 2020 - Springer
The manuscript reviews several selected applications of Activation Analysis that differ from
classical laboratory measurements by the fact that they do not require sampling of the …

Solubility and anisotropic migration behaviors of helium in bcc iron under strain

Y Yu, B Xu, H Chen, ZG Yang, C Zhang - Acta Metallurgica Sinica (English …, 2018 - Springer
The different solution and migration behaviors of tetrahedral and octahedral interstitial
helium in bcc iron have been investigated by using first principles calculations. We showed …