Crystal Plasticity Model of Reactor Pressure Vessel Embrittlement in GRIZZLY
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.
- Publication Date:
- OSTI Identifier:
- Report Number(s):
- DOE Contract Number:
- Resource Type:
- Technical Report
- Research Org:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Org:
- USDOE Office of Nuclear Energy (NE)
- Country of Publication:
- United States
- 22 GENERAL STUDIES OF NUCLEAR REACTORS; 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
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