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Title: 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.
Authors:
 [1] ;  [1] ;  [1] ;  [1]
  1. Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Publication Date:
OSTI Identifier:
1244616
Report Number(s):
INL/EXT--15-35786
TRN: US1601045
DOE Contract Number:
AC07-05ID14517
Resource Type:
Technical Report
Research Org:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Org:
USDOE Office of Nuclear Energy (NE)
Country of Publication:
United States
Language:
English
Subject:
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