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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 Atomistic Simulation of Thermal and Irradiation Creep Mechanisms in BCC-Fe and FCC-Ni using Defect Rate-Based Long-time Dynamics
Author(s) Angel Chavira, Charles Hirst, Fei Gao, Kevin Field
On-Site Speaker (Planned) Angel Chavira
Abstract Scope Generation IV nuclear reactor components, such as fuel cladding, experience high temperatures, which limit their operational lifetime due to irradiation creep. Atomistic simulations can supplement experimental data by inferring creep mechanisms in the bulk material and at relevant timescales. Traditional methods, such as molecular dynamics and object kinetic Monte Carlo, struggle to simulate irradiation creep mechanisms due to time scale limitations or the high uncertainty associated with predefined diffusion paths. We employed Defect Rate-based Long-time Dynamics (DRLD) to study creep. DRLD is novel atomistic kinetic Monte Carlo code that uses ‘on-the-fly’ transition state search methods and defect preselection to accelerate dynamics to a timescale of seconds. With DRLD, we studied defect diffusion patterns with and without uniaxial stress in pure bcc-Fe and fcc-Ni systems. We will describe potential creep diffusion mechanisms of vacancy type defects at 450°C and 550°C. These findings inform potential irradiation creep mechanisms in experiments.
Proceedings Inclusion? Planned:
Keywords Computational Materials Science & Engineering, Nuclear Materials, Modeling and Simulation

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

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