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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 Comparison of Hardening and Microstructures of Structural Alloys Irradiated with Fast Neutrons and Dual Ions
Author(s) July Reyes-Zacarias, Stephen Taller, Steven J. Zinkle
On-Site Speaker (Planned) July Reyes-Zacarias
Abstract Scope Ferritic/martensitic steels T91 and HT9, along with austenitic alloy 800H, were irradiated with fission neutrons from the BOR-60 reactor, and dual ions (9 MeV Fe3+ and 3.42 MeV energy-degraded He2+) at temperatures ranging from 370 to 520 °C and damage levels from 17 to 72 dpa. This study aimed to quantify the similarities and differences between ion and neutron irradiation on microstructures and mechanical properties, in order to develop methods for accelerating the screening and qualification of new structural materials for nuclear energy applications. Nanoindentation testing was conducted to measure the bulk equivalent hardness of dual-ion irradiated samples. For the neutron-irradiated samples, both nanoindentation and Vickers hardness tests were carried out. Transmission Electron Microscopy (TEM) was used to characterize cavities, dislocation loops, and precipitates to evaluate their contributions to the overall strengthening of each alloy as a function of irradiation conditions.
Proceedings Inclusion? Planned:
Keywords Nuclear Materials,

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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