SCC evaluation of candidate container alloys by DCB method
Description
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
Availability note (English)
Available from PURL: https://www.osti.gov/servlets/purl/750368-gV8Q0S/webviewable/Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 3.0 Megabytes
- Report number
- UCRL-JC--135975
Conference
- Title
- Corrosion/2000 Conference
- Dates
- 26-31 Mar 2000
- Place
- Orlando, FL (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 32032755
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CANDU TYPE REACTORS; FRACTURE PROPERTIES; HYDROGEN EMBRITTLEMENT; INTERSTITIAL HYDROGEN GENERATION; NIOBIUM ALLOYS; PRESSURE TUBES; STRESS CORROSION; ZIRCONIUM ALLOYS
- Descriptors DEC
- ALLOYS; CHEMICAL REACTIONS; CORROSION; EMBRITTLEMENT; HEAVY WATER MODERATED REACTORS; MECHANICAL PROPERTIES; PHYSICAL RADIATION EFFECTS; POWER REACTORS; PRESSURE TUBE REACTORS; RADIATION EFFECTS; REACTORS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; TUBES
Optional Information
- Contract/Grant/Project number
- W-7405-ENG-48
- Notes
- This record replaces 31015357
- Funding organization
- USDOE Office of Civilian Radioactive Waste Management (Rwanda) (US)