skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: FY17 CAES LDRD Annual Report

Abstract

Metallic alloys are widely used or planned for use as structural and cladding materials in current and future reactors. Under irradiation, grain boundary (GB) cohesion strength decreases due to interaction with defects and impurities, leading to intergranular fracture and embrittlement of alloys. The objective of this project is to develop a technique for quantifying GB cohesion and its impact on fracture behavior in irradiated alloys, by utilizing transmission electron microscopic (TEM) in situ cantilever testing in concert with multi-scale modeling. The TEM in situ cantilever testing is a novel approach for studying the real-time mechanical response of materials. It will be used in this work for studying intergranular fracture behavior in several irradiated iron-based ferritic alloys and providing key information to link atomistic level events with mesoscale/macroscopic mechanical properties. The Multi-Physics Object-Oriented Simulation Environment (MOOSE)-based cohesive zone model (CZM) and extended finite element method (XFEM) for intergranular fracture of irradiated ferritic alloys will be developed in this work by utilizing atomistic results as inputs and experimental results for validation.

Authors:
 [1];  [1];  [2];  [3];  [4]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
  2. Boise State Univ., Boise, ID (United States)
  3. Univ. of Idaho, Moscow, ID (United States)
  4. Univ. of Wyoming, Laramie, WY (United States)
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1472089
Report Number(s):
INL/EXT-17-43229-Rev000
DOE Contract Number:  
AC07-05ID14517
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; Grain Boundary; Cohesion; Irradiation

Citation Formats

Jiang, Chao, Jiang, Wen, Jaques, Brian, Charit, Indrajit, and Fertig, Ray. FY17 CAES LDRD Annual Report. United States: N. p., 2017. Web. doi:10.2172/1472089.
Jiang, Chao, Jiang, Wen, Jaques, Brian, Charit, Indrajit, & Fertig, Ray. FY17 CAES LDRD Annual Report. United States. doi:10.2172/1472089.
Jiang, Chao, Jiang, Wen, Jaques, Brian, Charit, Indrajit, and Fertig, Ray. Fri . "FY17 CAES LDRD Annual Report". United States. doi:10.2172/1472089. https://www.osti.gov/servlets/purl/1472089.
@article{osti_1472089,
title = {FY17 CAES LDRD Annual Report},
author = {Jiang, Chao and Jiang, Wen and Jaques, Brian and Charit, Indrajit and Fertig, Ray},
abstractNote = {Metallic alloys are widely used or planned for use as structural and cladding materials in current and future reactors. Under irradiation, grain boundary (GB) cohesion strength decreases due to interaction with defects and impurities, leading to intergranular fracture and embrittlement of alloys. The objective of this project is to develop a technique for quantifying GB cohesion and its impact on fracture behavior in irradiated alloys, by utilizing transmission electron microscopic (TEM) in situ cantilever testing in concert with multi-scale modeling. The TEM in situ cantilever testing is a novel approach for studying the real-time mechanical response of materials. It will be used in this work for studying intergranular fracture behavior in several irradiated iron-based ferritic alloys and providing key information to link atomistic level events with mesoscale/macroscopic mechanical properties. The Multi-Physics Object-Oriented Simulation Environment (MOOSE)-based cohesive zone model (CZM) and extended finite element method (XFEM) for intergranular fracture of irradiated ferritic alloys will be developed in this work by utilizing atomistic results as inputs and experimental results for validation.},
doi = {10.2172/1472089},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2017},
month = {9}
}

Technical Report:

Save / Share: