Fission recoil-induced microstructural evolution of the fuel-cladding interface [FCI] in high burnup BWR fuel
Understanding the structural evolution of nuclear fuel and cladding during operation is essential for predicting performance during and after service in a light water reactor. In this work, we utilized focused ion beam-based preparation techniques to make transmission electron microscopy samples of the cross-section of the fuel-cladding interface oxide region of high burn-up BWR fuel. Using diffraction contrast STEM imaging and precession electron diffraction, we demonstrated that not only does fission product radiation stabilize the tetragonal phase of zirconium oxide at temperatures well below the equilibrium temperature, but it also causes grain growth that is proportional to the fission production radiation damage. The tetragonal phase ZrO2 was exclusively present only in the region where fission product metal particles were found (~6µm), and then the tetragonal phase was also present, but mixed with monoclinic phase, up to the max depth at which fission product radiation is expected to be reached - ~8µm. Also, the grain size distribution of tetragonal phase was proportional to the integrated damage (excess vacancies generated) profile of the implanted fission product atoms.
- Research Organization:
- Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
- Sponsoring Organization:
- USDOE
- Grant/Contract Number:
- AC05-76RL01830
- OSTI ID:
- 1547444
- Alternate ID(s):
- OSTI ID: 1543318
- Report Number(s):
- PNNL-SA-139875; S0022311519300224; PII: S0022311519300224
- Journal Information:
- Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 521 Journal Issue: C; ISSN 0022-3115
- Publisher:
- ElsevierCopyright Statement
- Country of Publication:
- Netherlands
- Language:
- English
Web of Science
Distribution of metallic fission-product particles in the cladding liner of spent nuclear fuel
|
journal | January 2020 |
A new non-diffusional gas bubble production route in used nuclear fuel: implications for fission gas release, cladding corrosion, and next generation fuel design
|
journal | January 2020 |
Similar Records
Electron microscopy characterization of the fuel-cladding interaction in medium burnup annular fast reactor MOX
Corrosion and hydrogen pick-up behaviors of cladding and structural components in BWR high burnup 9x9 lead use assemblies