SCC evaluation of candidate container alloys by DCB method
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.
- Research Organization:
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
- Sponsoring Organization:
- USDOE Office of Civilian Radioactive Waste Management (RW) (US)
- DOE Contract Number:
- W-7405-ENG-48
- OSTI ID:
- 750368
- Report Number(s):
- UCRL-JC-135975; TRN: US0000662
- 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
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