ProgramMaster Logo
Conference Tools for 2023 TMS Annual Meeting & Exhibition
Login
Register as a New User
Help
Submit An Abstract
Propose A Symposium
Presenter/Author Tools
Organizer/Editor Tools
About this Abstract
Meeting 2023 TMS Annual Meeting & Exhibition
Symposium Transmutation Effects in Fusion Reactor Materials: Critical Challenges & Path Forward
Presentation Title Analytical TEM Examination of Re and Os Segregation in Neutron Irradiated Tungsten
Author(s) Michael Klimenkov, Ute Jäntsch, Michael Dürrschnabel, Michael Rieth, Dmitry Terentyev, Wouter Van Renterghem
On-Site Speaker (Planned) Michael Klimenkov
Abstract Scope Tungsten is the prime candidate material for plasma-facing components in future fusion reactors due to its several advantageous properties such as a high melting point, high sputtering resistance and low coefficient of thermal expansion. The transmission electron microscopic examination tungsten irradiated in BR2 reactor at various temperatures and damage neutron irradiated tungsten is of high importance for assessing possible limits of operation conditions and life-time of plasma facing components. This work focuses on the analysis of temperature- and dose-dependent rhenium (Re) and osmium (Os) segregation at voids, dislocation loops and grain boundaries. Segregation processes lead to a local Re and Os enrichment under certain conditions formation of σ-W(ReOs)2 and χ-W(ReOs)3 precipitates. The results contribute not only to the understanding of radiation hardening and embrittlement, which significantly limit the lifetime of W devices, but also to the verification and improvement of theoretical models for radiation-induced Re and Os diffusion in W.
Proceedings Inclusion? Planned:
Keywords Nuclear Materials,

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Ab Initio and Classical Molecular Dynamics Study of Re Transport in W
Ab Initio Study of Tungsten-based Alloys Under Fusion Power-plant Conditions
Accurate Fe-He Machine Learning Potential for Studying Helium Effects in Ferritic Steels
Advanced Synchrotron Characterization Techniques for Fusion Materials Science
Analysis of Irradiation Damage Accumulation in Bi-phase Tungsten Heavy Alloy Microstructures
Analytical TEM Examination of Re and Os Segregation in Neutron Irradiated Tungsten
Behavior of Helium Cavities in Ion-irradiated Ductile-Phase-Toughened Tungsten
Characterizing Transmutation Products in Materials via STEM and Machine Learning
Co-Segregation of Transmuted Re and Os in Neutron Irradiated Tungsten: First-principles Prediction and Experimental Validation
Critical Evaluation of High Temperature Helium Embrittlement Phenomena in Structural Materials
Discrete and Continuum Models for the Sources of Nonlinear Strain for Macrscopic Simulations of Reactor Components
Effect of Helium on Low-temperature Hardening/Embrittlement (LTHE) in Neutron Irradiated Isotopically Tailored RAFM Steels
Effects of Carbide Dispersoids on Helium Bubble Formation in Dispersion-strengthened Tungsten
Experimental Validation of Simulated Transmutation Predictions for Fusion Materials
Grain-boundary Effects on the Irradiated Damages in W-Re Alloys
He Irradiation of W First-wall Materials: Parameters at Stake for the Bubble Creation, Behaviour and Impact on Tritium Trapping
Helium Effects on Mechanical Properties of (RA)FM Steels
Helium Production in Irradiated Low-temperature Solder Candidates for Novel Fusion Magnet Cables
Impact of Pre-existing Damage on He Irradiated Sintered 3C-SiC
In-situ Helium Bubble Formation and Thermal Evolution in Lithium Metatitanate
Interaction of Hydrogen/Helium with Grain Boundaries and Dislocations in Tungsten
Investigation of High Temperature He Embrittlement Effects in High Performance Nickel-based Alloys
Irradiation Spectrum, Transmutation, and Supporting Materials Use Next Generation Fusion Systems
Machine-learned Interatomic Potential Development for H Trapping in ZrC Strengthened W
Machine Learning Generation of Trajectories for Accurate Modeling Plasma Material Interactions
Magic Numbers on the Shape of Voids Formed by Electron Irradiation in Aluminium
Modeling the Effect of He/dpa Rate on Microstructural Evolution in Ferritic-martensitic Alloys
Modelling of Re/Os Transmutation Product Segregation in Irradiated W Using Atomistic Kinetic Monte Carlo
Molecular Dynamics Simulations of Mixed Materials Effects in Tungsten
No Ball Milling Needed: Revamping Fabrication Route of ODS Steel Plate with Cold Spray and Friction Stir Processing
O-16: Microstructural Investigation of Irradiated REBCO Coated Conductors for Future HTS Fusion Magnets and Other High-dose Environments
Optimization of Tritium Breeding in Molten Salt Blankets: Materials and Geometries
Stability of a Li2TiO3 Candidate Solid-breeder Material Following Li Transmutation
Studies on Transmutation Effects in Reduced Activation Ferritic/Martensitic Steels in Japan
Suppression of Rhenium and Osmium Production in Tungsten-based Materials for Fusion Energy
Synergistic Effects between Radiation Damage and H/He Co-Injection on Swelling in Candidate Fusion Structural Materials
The Effect of Chemical Element Inventory Evolution on Recoil Production and Its Effect on Defect Cluster Evolution in Tungsten
The Effect of Helium on Cavity Swelling in Dual-ion Irradiated Fe and Fe-10Cr Ferritic Alloys
The Effects of High-dose He and H Ion Implantation on the Microstructural Development in EUROFER-ODS Steel
Thermonuclear Fusion: Some Open Issues Concerning Tritium
Tracking Neutron-irradiation Induced Transmutation Using Atom Probe Tomography and Neutron Inventory Calculations
Transmutation Effects in Fine Grained Tungsten: Gas Behavior and the Role of Grain Boundaries
Ultrafast Measurement of Microscopic Energy Flow in He-implanted W

Questions about ProgramMaster? Contact programming@programmaster.org