Libang Lai

Mr. Libang Lai

orcid

Research Focus & Metrics

Academic Career Length

4Years (2023-Present)

(Calculated once Scilit publication data is synced: current year − year of first publication + 1)

Representative Publications

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8 June 2025 in Materials Science and Engineering: A
Verified
Journal Article
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Wangzhong MuWangzhong Mu
Wangzhong Mu
ADAlexander Dahlström
Alexander Dahlström
LLLibang Lai
Libang Lai
CFCamille Flament
Camille Flament
JGJean-Marie Gentzbittel
Jean-Marie Gentzbittel
PHPeter Hedström
Peter Hedström

26 July 2023 in Metals
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Journal Article
Open access
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LLLibang Lai
Libang Lai
PCPaul Chekhonin
Paul Chekhonin
SAShavkat Akhmadaliev
Shavkat Akhmadaliev
JBJann-Erik Brandenburg
Jann-Erik Brandenburg
FBFrank Bergner
Frank Bergner
Ion irradiation is a promising tool to emulate neutron-irradiation effects on reactor pressure vessel (RPV) steels, especially in the situation of limited availability of suitable neutron-irradiated material. This approach requires the consideration of ion-neutron transferability issues, which are addressed in the present study by comparing the effect of ions with neutron-irradiation effects reported for the same materials. The first part of the study covers a comprehensive characterization, based on dedicated electron microscopy techniques, of the selected unirradiated RPV materials, namely a base metal and a weld. The results obtained for the grain size, dislocation density, and precipitates are put in context in terms of hardening contributions and sink strength. The second part is focused on the depth-dependent characterization of the dislocation loops formed in ion-irradiated samples. This work is based on scanning transmission electron microscopy applied to cross-sectional samples prepared by the focused ion beam technique. A band-like arrangement of loops is observed in the depth range close to the peak of injected interstitials. Two levels of displacement damage, 0.1 and 1 dpa (displacements per atom), as well as post-irradiation annealed conditions, are included for both RPV materials. Compared with neutron irradiation, ion irradiation creates a similar average size but a higher number density of loops presumably due to the higher dose rate during ion irradiation.

21 February 2024 in Metals
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Journal Article
Open access
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LLLibang Lai
Libang Lai
JBJann-Erik Brandenburg
Jann-Erik Brandenburg
PCPaul Chekhonin
Paul Chekhonin
ADArnaud Duplessi
Arnaud Duplessi
FCFabien Cuvilly
Fabien Cuvilly
FBFrank Bergner
Frank Bergner
Ion irradiation combined with nanoindentation is a promising tool for studying irradiation-induced hardening of nuclear materials, including reactor pressure vessel (RPV) steels. For RPV steels, the major sources of hardening are nm-sized irradiation-induced dislocation loops and solute atom clusters, both representing barriers for dislocation glide. The dispersed barrier hardening (DBH) model provides a link between the irradiation-induced nanofeatures and hardening. However, a number of details of the DBH model still require consideration. These include the role of the unirradiated microstructure, the proper treatment of the indentation size effect (ISE), and the appropriate superposition rule of individual hardening contributions. In the present study, two well-characterized RPV steels, each ion-irradiated up to two different levels of displacement damage, were investigated. Dislocation loops and solute atom clusters were characterized by transmission electron microscopy and atom probe tomography, respectively. Nanoindentation with a Berkovich indenter was used to measure indentation hardness as a function of the contact depth. In the present paper, the measured hardening profiles are compared with predictions based on different DBH models. Conclusions about the appropriate superposition rule and the consideration of the ISE (in terms of geometrically necessary dislocations) are drawn.