Effects of oxidation and inter-diffusion on the fracture mechanisms of Cr-coated Zry-4 alloys: An in situ three-point bending study
- 1. Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-Sen University, Zhuhai 519082, Guangdong (China)
Description
Highlights: • Different cracking modes of pre-oxidised and vacuum-annealed Cr coatings were studied. • Crack resistance of Cr coating was greatly enhanced due to recrystallization effect. • The brittle diffusion layer was easier to generate micro-cracks under external loadings. • Oxygen transportation, inter-diffusion and phase transformation led to pre-failure of Cr coatings. Chromium (Cr)-coated zirconium alloys have been considered as a promising candidate material for accident-tolerant fuel (ATF) cladding for nuclear reactors because of their superior oxidation resistance under accident conditions. However, the oxidation and diffusion behaviours that occur in the Cr coating–Zr substrate system at high temperatures significantly affect the microstructure and mechanical properties of the coating, leading to cracking modes that are distinct from those of the as-deposited coating. To understand the effects of oxidation and inter-diffusion on the fracture mechanisms of Cr-coated Zry-4 alloys, in situ three-point bending tests were conducted in this study. Crack initiation and propagation in the oxidised and vacuum-annealed coatings were observed in real time. The results showed that high-temperature exposure led to recrystallisation of the Cr coating (columnar grains transformed into equiaxed grains), which greatly enhanced the crack resistance of the Cr coating. However, a diffusion-induced intermetallic ZrCr2 layer and an α-Zr(O) layer (which transformed from β-Zr owing to oxygen transportation) formed simultaneously at the coating/substrate interface. The micro-cracks formed in these brittle layers rapidly penetrated all the layers under external load, leading to premature failure of the coated sample.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.matdes.2021.110168Additional details
Identifiers
- DOI
- 10.1016/j.matdes.2021.110168;
- PII
- S0264127521007231;
Publishing Information
- Journal Title
- Materials and Design
- Journal Volume
- 212
- Journal Page Range
- vp.
- ISSN
- 0264-1275
- CODEN
- MADSD2
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 54033297
- Subject category
- S36: MATERIALS SCIENCE; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Descriptors DEI
- ACCIDENT-TOLERANT NUCLEAR FUELS; CHROMIUM; CLADDING; CRACK PROPAGATION; CRACKING; CRACKS; FRACTURES; INTERMETALLIC COMPOUNDS; MECHANICAL PROPERTIES; MICROSTRUCTURE; OXIDATION; OXYGEN; PHASE TRANSFORMATIONS; RECRYSTALLIZATION; SUBSTRATES; ZIRCONIUM ALLOYS; ZIRCONIUM-ALPHA; ZIRCONIUM-BETA
- Descriptors DEC
- ALLOYS; CHEMICAL REACTIONS; DECOMPOSITION; DEPOSITION; ELEMENTS; ENERGY SOURCES; FAILURES; FUELS; MATERIALS; METALS; NONMETALS; NUCLEAR FUELS; PYROLYSIS; REACTOR MATERIALS; SURFACE COATING; THERMOCHEMICAL PROCESSES; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENTS; ZIRCONIUM
Optional Information
- Copyright
- Copyright (c) 2021 The Authors. Published by Elsevier Ltd.