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Meeting 2025 TMS Annual Meeting & Exhibition
Symposium Special Topics in Nuclear Materials: Lessons Learned; Non-Energy Systems; and Coupled Extremes
Presentation Title GIRAFFE – In Situ Material TestsUnder Fusion-Relevant Conditions
Author(s) Johann Riesch, Alexander Feichtmayer, Marcel Appel, Max Boleininger, Sebastian Estermann, Till Höschen, Thomas Schwarz-Selinger, Sergei L. Dudarev, Rudolf Neu
On-Site Speaker (Planned) Johann Riesch
Abstract Scope In a future fusion reactor, the synergistic effects of irradiation damage, hydrogen, impurities such as helium, and mechanical stresses will significantly affect the properties of the materials used. To study this, the General-Purpose Irradiated Fiber and Foil Experiment (Giraffe) was developed. Giraffe enables in situ mechanical testing with simultaneous irradiation by MeV energy ions (e.g. protons, tungsten) from a 3 MV tandem accelerator or keV ions from a plasma source (e.g. hydrogen, helium). The use of samples with a thickness of a few µm makes it possible to irradiate large volume fractions despite the very shallow penetration depth typical of ion irradiation. A sample environment control system allowing heating up to 1600°C and cooling down to -150°C is presently commissioned. In this contribution, an overview of the features of the device and the capabilities of the new methodology will be given as well as a summary of performed experiments.
Proceedings Inclusion? Planned:
Keywords Nuclear Materials, Characterization, Mechanical Properties

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Advancing Radioisotope Heat Sources: Enhancing RPS for Extreme Environments
Atomistic Simulation of Thermal and Irradiation Creep Mechanisms in BCC-Fe and FCC-Ni using Defect Rate-Based Long-time Dynamics
Best Practices for Irradiation Experiment Design For Nuclear Fuels and Materials Research
Cavity Formation Induced by Swift Heavy Ion Irradiation in AlN/GaN
Comparison of Hardening and Microstructures of Structural Alloys Irradiated with Fast Neutrons and Dual Ions
Developing a High-Performance Cluster Dynamics Code: Challenges and Lessons Learned
Effect of Applied Stress on Radiation-Induced Loop and Raft Formation in a BCC Metal
Effect of Tensile Stress Gradients on the Multi-Length-Scale Microstructure in Thermal and Irradiation Creep of 316L Stainless Steel
Energy Dispersive X-Ray Spectroscopy (EDS) Induced Defects and Implantation Induced Impurities in Uranium Nitride (UN) and SIMFUEL Pellets
Fabrication of Titanium-Containing Tri-Carbide Ultra-High Temperature Ceramics
GIRAFFE – In Situ Material TestsUnder Fusion-Relevant Conditions
In-situ Electron Microscopy Characterization of Deformation Mechanisms of Inconel 718 Irradiated with Simultaneous High Energy Protons and Spallation Neutrons
Influence of Radiation Swelling on Residual Stresses and Measurement of Micromechanical Properties
Materials Research for High-Power Accelerator Beam-Intercepting Devices
Modeling Galvanic Drawdown Separations Technique
Phase Field Modeling of Irradiation-Induced Amorphous-to-Crystalline (A-C) Transformations in Structural Ceramics
Post Irradiation Examination and Administrative Lifetime Limits of Highly Irradiated Components at The Spallation Neutron Source
Small Scale Tests, Big Lessons Learned
The Recovery of Irradiation Damage for Zircaloy-2 and Zircaloy-4 following Irradiation at Higher Temperatures of 377-410°C

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