Crystal Plasticity Model of Reactor Pressure Vessel Embrittlement in GRIZZLY
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
The integrity of reactor pressure vessels (RPVs) is of utmost importance to ensure safe operation of nuclear reactors under extended lifetime. Microstructure-scale models at various length and time scales, coupled concurrently or through homogenization methods, can play a crucial role in understanding and quantifying irradiation-induced defect production, growth and their influence on mechanical behavior of RPV steels. A multi-scale approach, involving atomistic, meso- and engineering-scale models, is currently being pursued within the GRIZZLY project to understand and quantify irradiation-induced embrittlement of RPV steels. Within this framework, a dislocation-density based crystal plasticity model has been developed in GRIZZLY that captures the effect of irradiation-induced defects on the flow stress behavior and is presented in this report. The present formulation accounts for the interaction between self-interstitial loops and matrix dislocations. The model predictions have been validated with experiments and dislocation dynamics simulation.
- Research Organization:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE)
- DOE Contract Number:
- AC07-05ID14517
- OSTI ID:
- 1244616
- Report Number(s):
- INL/EXT-15-35786; M3LW-15IN0704067; TRN: US1601045
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
36 MATERIALS SCIENCE
DISLOCATIONS
STEELS
PRESSURE VESSELS
PLASTICITY
CRYSTALS
EMBRITTLEMENT
FLOW STRESS
HOMOGENIZATION METHODS
CRYSTAL DEFECTS
DENSITY
IRRADIATION
MICROSTRUCTURE
REACTORS
COMPUTERIZED SIMULATION
MATHEMATICAL MODELS
G CODES
PHYSICAL RADIATION EFFECTS
MECHANICAL PROPERTIES
Crystal Plasticity
Irradiation embrittlement
RPV steel