Gradient Plasticity Model and its Implementation into MARMOT
- Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)
The influence of strain gradient on deformation behavior of nuclear structural materials, such as body-centered cubic (bcc) iron alloys has been investigated. We have developed and implemented a dislocation based strain gradient crystal plasticity material model. A mesoscale crystal plasticity model for inelastic deformation of metallic material, bcc steel, has been developed and implemented numerically. Continuum Dislocation Dynamics (CDD) with a novel constitutive law based on dislocation density evolution mechanisms was developed to investigate the deformation behaviors of single crystals, as well as polycrystalline materials by coupling CDD and crystal plasticity (CP). The dislocation density evolution law in this model is mechanism-based, with parameters measured from experiments or simulated with lower-length scale models, not an empirical law with parameters back-fitted from the flow curves.
- Research Organization:
- Pacific Northwest National Laboratory (PNNL), Richland, WA (United States). Nuclear Energy Advanced Modeling and Simulation (NEAMS)
- Sponsoring Organization:
- USDOE Office of Energy Efficiency and Renewable Energy (EERE)
- DOE Contract Number:
- AC05-76RL01830
- OSTI ID:
- 1133998
- Report Number(s):
- PNNL--22702; NT0108020
- Country of Publication:
- United States
- Language:
- English
Similar Records
A defect density-based constitutive crystal plasticity framework for modeling the plastic deformation of Fe-Cr-Al cladding alloys subsequent to irradiation
Dislocation Patterning in Deforming Crystals: Theory, Computational Predictions and Validation (Final Technical Report)
Report on Aging and Irradiation Theoretical Model Development for Alloy 690 in Grizzly
Technical Report
·
Thu Feb 04 23:00:00 EST 2016
·
OSTI ID:1237412
Dislocation Patterning in Deforming Crystals: Theory, Computational Predictions and Validation (Final Technical Report)
Technical Report
·
Fri Feb 24 23:00:00 EST 2023
·
OSTI ID:1958516
Report on Aging and Irradiation Theoretical Model Development for Alloy 690 in Grizzly
Technical Report
·
Fri Mar 30 00:00:00 EDT 2018
·
OSTI ID:1478527