Accident tolerant fuel cladding development: Promise, status, and challenges
Abstract
The motivation for transitioning away from zirconium-based fuel cladding in light water reactors to significantly more oxidation-resistant materials, thereby enhancing safety margins during severe accidents, is laid out. A review of the development status for three accident tolerant fuel cladding technologies, namely coated zirconium-based cladding, ferritic alumina-forming alloy cladding, and silicon carbide fiber–reinforced silicon carbide matrix composite cladding, is offered. Technical challenges and data gaps for each of these cladding technologies are highlighted. Full development towards commercial deployment of these technologies is identified as a high priority for the nuclear industry.
- Authors:
-
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Publication Date:
- Research Org.:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE Office of Nuclear Energy (NE)
- OSTI Identifier:
- 1471930
- Alternate Identifier(s):
- OSTI ID: 1506714
- Grant/Contract Number:
- AC05-00OR22725
- Resource Type:
- Journal Article: Accepted Manuscript
- Journal Name:
- Journal of Nuclear Materials
- Additional Journal Information:
- Journal Volume: 501; Journal Issue: C; Journal ID: ISSN 0022-3115
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 36 MATERIALS SCIENCE
Citation Formats
Terrani, Kurt A. Accident tolerant fuel cladding development: Promise, status, and challenges. United States: N. p., 2018.
Web. doi:10.1016/j.jnucmat.2017.12.043.
Terrani, Kurt A. Accident tolerant fuel cladding development: Promise, status, and challenges. United States. doi:10.1016/j.jnucmat.2017.12.043.
Terrani, Kurt A. Sat .
"Accident tolerant fuel cladding development: Promise, status, and challenges". United States. doi:10.1016/j.jnucmat.2017.12.043. https://www.osti.gov/servlets/purl/1471930.
@article{osti_1471930,
title = {Accident tolerant fuel cladding development: Promise, status, and challenges},
author = {Terrani, Kurt A.},
abstractNote = {The motivation for transitioning away from zirconium-based fuel cladding in light water reactors to significantly more oxidation-resistant materials, thereby enhancing safety margins during severe accidents, is laid out. A review of the development status for three accident tolerant fuel cladding technologies, namely coated zirconium-based cladding, ferritic alumina-forming alloy cladding, and silicon carbide fiber–reinforced silicon carbide matrix composite cladding, is offered. Technical challenges and data gaps for each of these cladding technologies are highlighted. Full development towards commercial deployment of these technologies is identified as a high priority for the nuclear industry.},
doi = {10.1016/j.jnucmat.2017.12.043},
journal = {Journal of Nuclear Materials},
issn = {0022-3115},
number = C,
volume = 501,
place = {United States},
year = {2018},
month = {1}
}
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Figures / Tables:
Figure 1.: Thermal power and cumulative energy due to radionuclide decay heat and Zr-based cladding oxidation heat during a short-term station blackout.
Figures / Tables found in this record: