About this Abstract |
Meeting |
2023 TMS Annual Meeting & Exhibition
|
Symposium
|
Mechanical Behavior of Nuclear Reactor Materials and Components III
|
Presentation Title |
A Mesoscale Model of Creep in Monolithic UMo Fuels |
Author(s) |
Shenyang Hu, Benjamin Beeler |
On-Site Speaker (Planned) |
Shenyang Hu |
Abstract Scope |
Experiments show that creep is one of failure modes in monolithic UMo fuels. Because gas bubbles act as sinks of defects and has different elastic-plastic properties from that of UMo matrix gas bubble structures (volume fraction, spatial and size distributions) not only affect defect concentrations, but also stresses, hence, the creep. In this talk, we will present a mesoscale model of creep by integrating a microstructure-dependent cluster dynamics model, a phase-field model of nonequilibrium gas bubbles, and crystal plasticity theory. The integrated model aims to capture the multi-physics coupling of radiation defect evolution, gas bubble evolution, and diffusion-controlled creep. The effect of radiation conditions, inhomogeneous kinetic properties of defects, and applied stresses on gas bubble swelling and creep rate in polycrystalline UMo and Zr layer structures will be presented. The results are important inputs in the development of creep rate model for predicting the fuel performance. |
Proceedings Inclusion? |
Planned: |
Keywords |
Modeling and Simulation, Nuclear Materials, Mechanical Properties |