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

Title: SCC evaluation of candidate container alloys by DCB method

Abstract

The authors use a solid mechanics approach to investigate hydride formation and cracking in zirconium-niobium alloys used in the pressure tubes of CANDU nuclear reactors. In this approach, the forming hydride is assumed to be purely elastic and its volume dilation is accommodated by elasto-plastic deformation of the surrounding matrix material. The energetics of the hydride formation is revisited and the terminal solid solubility of hydrogen in solution is defined on the basis of the total elasto-plastic work done on the system by the forming hydride and the external loads. Hydrogen diffusion and probabilistic hydride formation coupled with the material deformation are modeled at a blunting crack tip under plane strain loading. A full transient finite element analysis allows for numerical monitoring of the development and expansion of the hydride zone as the externally applied loads increase. Using a Griffith fracture criterion for fracture limitiation, the reduced fracture resistance of the alloy can be predicted and the factors affecting fracture toughness quantified.

Authors:
; ; ;
Publication Date:
Research Org.:
Lawrence Livermore National Lab., CA (US)
Sponsoring Org.:
USDOE Office of Civilian Radioactive Waste Management (RW) (US)
OSTI Identifier:
750368
Report Number(s):
UCRL-JC-135975
TRN: US0000662
DOE Contract Number:  
W-7405-ENG-48
Resource Type:
Conference
Resource Relation:
Conference: Corrosion/2000 Conference, Orlando, FL (US), 03/26/2000--03/31/2000; Other Information: PBD: 24 Sep 1999
Country of Publication:
United States
Language:
English
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; 36 MATERIALS SCIENCE; ZIRCONIUM ALLOYS; NIOBIUM ALLOYS; STRESS CORROSION; HYDROGEN EMBRITTLEMENT; PRESSURE TUBES; CANDU TYPE REACTORS; INTERSTITIAL HYDROGEN GENERATION; FRACTURE PROPERTIES

Citation Formats

Roy, A K, Freeman, D C, Lum, B Y, and Spragge, M K. SCC evaluation of candidate container alloys by DCB method. United States: N. p., 1999. Web.
Roy, A K, Freeman, D C, Lum, B Y, & Spragge, M K. SCC evaluation of candidate container alloys by DCB method. United States.
Roy, A K, Freeman, D C, Lum, B Y, and Spragge, M K. Fri . "SCC evaluation of candidate container alloys by DCB method". United States. https://www.osti.gov/servlets/purl/750368.
@article{osti_750368,
title = {SCC evaluation of candidate container alloys by DCB method},
author = {Roy, A K and Freeman, D C and Lum, B Y and Spragge, M K},
abstractNote = {The authors use a solid mechanics approach to investigate hydride formation and cracking in zirconium-niobium alloys used in the pressure tubes of CANDU nuclear reactors. In this approach, the forming hydride is assumed to be purely elastic and its volume dilation is accommodated by elasto-plastic deformation of the surrounding matrix material. The energetics of the hydride formation is revisited and the terminal solid solubility of hydrogen in solution is defined on the basis of the total elasto-plastic work done on the system by the forming hydride and the external loads. Hydrogen diffusion and probabilistic hydride formation coupled with the material deformation are modeled at a blunting crack tip under plane strain loading. A full transient finite element analysis allows for numerical monitoring of the development and expansion of the hydride zone as the externally applied loads increase. Using a Griffith fracture criterion for fracture limitiation, the reduced fracture resistance of the alloy can be predicted and the factors affecting fracture toughness quantified.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1999},
month = {9}
}

Conference:
Other availability
Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that hold this conference proceeding.

Save / Share: