G. Bonny

Belgian Nuclear Research Centre — Belgium

Materials Science · Physical Sciences

34h-index4.0kcitations132works1.82yr avg
OpenAlex↗ORCID↗Google Scholar↗Lab page↗

Accepting Students?

No reports yet. Know if this professor is taking students?

Research Topics

Fusion materials and technologies(82), Nuclear Materials and Properties(76), High Temperature Alloys and Creep(25), Microstructure and mechanical properties(18), Advanced materials and composites(15)

Publications132 total

Numerical investigations on size effects and mini-CT applications for Master Curve determination
Engineering Fracture Mechanics·2025
Link between material properties and integrity assessment of NPP components within EU funded projects APAL, INCEFA-SCALE and FRACTESUS
EPJ Nuclear Sciences & Technologies·2025Open Access
On the capabilities of k-ART over MD for the study of the kinetics of small point defect clusters in α-Fe
Journal of Nuclear Materials·2024· 3 citedOpen Access
Present Status of the FRACTESUS Project: Numerical and Experimental Round Robins on Irradiated and Unirradiated Materials
2024· 2 citedOpen Access
Project FRACTESUS: Fracture Toughness Round Robin on a High Copper Weld Using Miniature C(T) Specimens – Results and Discussion
2024Open Access
How precisely are solute clusters in RPV steels characterized by atom probe experiments?
arXiv (Cornell University)·2024Open Access
Physical insight into interactions of interstitial loops and dislocation lines in austenitic high entropy alloys: atomic-scale modelling
Journal of Nuclear Materials·2024· 9 citedOpen Access
On the Capabilities of K-Art Over Molecular Dynamics for the Study of the Kinetics of Small Point Defect Clusters in Α-Fe
SSRN Electronic Journal·2024Open Access
The UO <sub>2</sub> Power-to-Melt Experiment Performed in the High Burnup Chemistry International Program
Nuclear Technology·2023· 3 citedOpen Access
Modeling of OECD/NEA P2M Benchmark Cases by Means of TRANSURANUS Code
Nuclear Technology·2023· 1 cited
The Effect of Loss of Constraint on the Initiation of Ductile Fracture in a Mini-CT
2023· 4 citedOpen Access
Present Status of the Fractesus Project: Round Robin on Unirradiated Materials
2023· 3 citedOpen Access
The strong hardening effect of Re segregation on edge dislocation lines in W
Computational Materials Science·2023· 1 cited
P2M Simulation Exercise on Past Fuel Melting Irradiation Experiments
Nuclear Technology·2023· 11 citedOpen Access
Defect evolution of neutron irradiated ITER grade tungsten after annealing
Fusion Engineering and Design·2023· 8 cited
On the microstructure evolution in tungsten ITER monoblocks: A computational study
Computational Materials Science·2023· 7 cited
FRACTESUS Project overview: objectives, organisation and initial findings
Procedia Structural Integrity·2023· 3 citedOpen Access
Development of RAFM steels for high temperature applications guided by thermodynamic modelling
Nuclear Materials and Energy·2022· 16 citedOpen Access
The combined effect of carbon and chromium enrichment on 〈1 0 0〉 loop absorption in iron
Computational Materials Science·2022· 9 cited
TEM investigation of neutron irradiated and post irradiation annealed tungsten materials
Fusion Engineering and Design·2022· 12 cited
page 1 of 7Next →

Frequent Co-authors

D. Terentyev(28), L. Malerba(25), A. Bakaev(17), N. Castin(15), Е. Е. Журкин(10), R.C. Pasianot(8), Pär Olsson(7), D. Terentyev(6), Christophe Domain(6), Petr Grigorev(4), Dimitri Van Neck(4), M.J. Konstantinović(4), Andrea E. Sand(3), Yuri A. Mastrikov(3), Chao Yin(3), A. Dubinko(3), C.J. Ortiz(3), M. Hou(2), S. L. Dudarev(2), Chu‐Chun Fu(2)