E. Gaganidze
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View article: <i>In-situ</i> S/TEM investigations of deformation and damage mechanisms in neutron-irradiated EUROFER97
<i>In-situ</i> S/TEM investigations of deformation and damage mechanisms in neutron-irradiated EUROFER97 Open
In this work, we employed in-situ S/TEM techniques to investigate deformation and damage mechanisms in neutron-irradiated reduced-activation ferritic/martensitic (RAFM) EUROFER97 steel subjected to a dose of 15 dpa at 330 °C. The irradiate…
View article: Investigation of microstructural evolution of irradiation-induced defects in tungsten: an experimental–numerical approach
Investigation of microstructural evolution of irradiation-induced defects in tungsten: an experimental–numerical approach Open
This study employs an integrated experimental–numerical approach to assess the microstructural evolution of irradiation-induced defects in tungsten (W), which is being considered for fusion applications. A cluster dynamics (CD) model is ut…
View article: Investigation of microstructural evolution of irradiation-induced defects in tungsten: an experimental-numerical approach
Investigation of microstructural evolution of irradiation-induced defects in tungsten: an experimental-numerical approach Open
The hostile condition in a fusion tokomak reactor poses the main challenge in the development and design of in-vessel components such as divertor and breeding blanket due to fusion relevant irradiation conditions (14 MeV) and large thermal…
View article: Investigation of Microstructural Evolution of Irradiation-Induced Defects in Tungsten: An Experimental-Numerical Approach
Investigation of Microstructural Evolution of Irradiation-Induced Defects in Tungsten: An Experimental-Numerical Approach Open
View article: In-Situ S/Tem Investigations of Deformation and Damage Mechanism of Neutron-Irradiated Eurofer97
In-Situ S/Tem Investigations of Deformation and Damage Mechanism of Neutron-Irradiated Eurofer97 Open
View article: Embrittlement of WCLL blanket and its fracture mechanical assessment
Embrittlement of WCLL blanket and its fracture mechanical assessment Open
In the European fusion programme, the Water Cooled Lithium Lead breeding blanket (WCLL BB) uses EUROFER as a structural material cooled with water at temperatures between 295 °C–328 °C and a pressure of 155 bar. The WCLL BB will be signifi…
View article: Present Status of the Fractesus Project: Round Robin on Unirradiated Materials
Present Status of the Fractesus Project: Round Robin on Unirradiated Materials Open
The present paper provides a summary of an inter-laboratory round robin on the fracture toughness testing and Master Curve application on unirradiated materials. First, a validation exercise was performed on the analysis of a given force-d…
View article: Master Curve Evaluation Using Miniature C(T) Specimens as Part of a Round Robin Program Within the FRACTESUS Project
Master Curve Evaluation Using Miniature C(T) Specimens as Part of a Round Robin Program Within the FRACTESUS Project Open
Surveillance testing is the basis for all reactor pressure vessel (RPV) integrity and lifetime assessments to evaluate the validity of the RPV embrittlement trend curve used for a specific reactor. Most of the standard surveillance program…
View article: Numerical Prediction of Fracture Toughness of a Reactor Pressure Vessel Steel Based on Experiments Using Small Specimens
Numerical Prediction of Fracture Toughness of a Reactor Pressure Vessel Steel Based on Experiments Using Small Specimens Open
Due to limited availability of irradiated material and safety concerns when testing large, irradiated specimens, a major effort is being made in nuclear materials research to establish small specimen testing techniques for determining the …
View article: Effect of neutron irradiation to 0.7 and 1.4 dpa on the tensile mechanical properties and microstructure of EUROFER97 steel
Effect of neutron irradiation to 0.7 and 1.4 dpa on the tensile mechanical properties and microstructure of EUROFER97 steel Open
View article: Macro-scale modeling of finite strain viscoplasticity in irradiated F/M steels: a continuum thermodynamic framework
Macro-scale modeling of finite strain viscoplasticity in irradiated F/M steels: a continuum thermodynamic framework Open
The European reduced activation ferritic/martensitic steel Eurofer97 in irradiated states displays significant nonlinear material behavior involving irradiation hardening, loss of strain hardening, and uniform elongation, as well as irradi…
View article: Recent progress in the assessment of irradiation effects for in-vessel fusion materials: tungsten and copper alloys
Recent progress in the assessment of irradiation effects for in-vessel fusion materials: tungsten and copper alloys Open
The present contribution highlights results of the recent irradiation campaigns applied to screen mechanical properties of advanced tungsten and copper-based materials—main candidates for the application in the plasma-facing components (PF…
View article: Multiscale modelling for fusion and fission materials: The M4F project
Multiscale modelling for fusion and fission materials: The M4F project Open
View article: The EUROfusion materials property handbook for DEMO in-vessel components—Status and the challenge to improve confidence level for engineering data
The EUROfusion materials property handbook for DEMO in-vessel components—Status and the challenge to improve confidence level for engineering data Open
The development of a specific materials database and handbook, for engineering design of in-vessel components of EU-DEMO, is an essential requirement for assessing the structural integrity by design. For baseline in-vessel materials, inclu…
View article: Nano-hardening features in high-dose neutron irradiated Eurofer97 revealed by atom-probe tomography
Nano-hardening features in high-dose neutron irradiated Eurofer97 revealed by atom-probe tomography Open
International audience
View article: Integrated Modeling of Helium-Vacancy Clustering in Eurofer97 Steel Upon He+/Fe3+ Dual Ion Beam Irradiation
Integrated Modeling of Helium-Vacancy Clustering in Eurofer97 Steel Upon He+/Fe3+ Dual Ion Beam Irradiation Open
View article: Ferritic-martensitic steels for fission and fusion applications
Ferritic-martensitic steels for fission and fusion applications Open
View article: Review and critical assessment of dislocation loop analyses on EUROFER 97
Review and critical assessment of dislocation loop analyses on EUROFER 97 Open
The understanding of microstructural defects behavior after neutron irradiation is crucial for assessing the applicability of reduced activation ferritic/martensitic (RAFM) steel EUROFER 97 in future fusion reactors. Formation and evolutio…
View article: Investigation of microstructure defects in EUROFER97 under He+/Fe3+ dual ion beam irradiation
Investigation of microstructure defects in EUROFER97 under He+/Fe3+ dual ion beam irradiation Open
View article: Development of benchmark reduced activation ferritic/martensitic steels for fusion energy applications
Development of benchmark reduced activation ferritic/martensitic steels for fusion energy applications Open
Reduced-activation ferritic/martensitic (RAFM) steel is the benchmark structural material for in-vessel components of fusion reactor. The current status of RAFM developments and evaluations is reviewed based on two leading RAFM steels, F82…
View article: Mechanical characterization of electrochemically based W – Cu joints for low-temperature heat sink application
Mechanical characterization of electrochemically based W – Cu joints for low-temperature heat sink application Open
View article: Choice of a low operating temperature for the DEMO EUROFER97 divertor cassette
Choice of a low operating temperature for the DEMO EUROFER97 divertor cassette Open
View article: Development of EUROFER97 database and material property handbook
Development of EUROFER97 database and material property handbook Open
View article: Microstructural defects in EUROFER 97 after different neutron irradiation conditions
Microstructural defects in EUROFER 97 after different neutron irradiation conditions Open
Characterization of irradiation induced microstructural evolution is essential for assessing the applicability of structural steels like the Reduced Activation Ferritic/Martensitic steel EUROFER 97 in upcoming fusion reactors. In this work…
View article: Comparative small angle neutron scattering (SANS) study of Eurofer97 steel neutron irradiated in mixed (HFR) and fast spectra (BOR60) reactors
Comparative small angle neutron scattering (SANS) study of Eurofer97 steel neutron irradiated in mixed (HFR) and fast spectra (BOR60) reactors Open
View article: Microstructural defects in EUROFER 97 after different neutron irradiation conditions
Microstructural defects in EUROFER 97 after different neutron irradiation conditions Open
Characterization of irradiation induced microstructural evolution is essential for assessing the applicability of structural steels like the Reduced Activation Ferritic/Martensitic steel EUROFER 97 in upcoming fusion reactors. In this work…
View article: Microstructural characterization of Eurofer-97 and Eurofer-ODS steels before and after multi-beam ion irradiations at JANNUS Saclay facility
Microstructural characterization of Eurofer-97 and Eurofer-ODS steels before and after multi-beam ion irradiations at JANNUS Saclay facility Open