Accident tolerant fuel cladding development: Promise, status, and challenges

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 te...

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Veröffentlicht in:	Journal of nuclear materials Jg. 501; H. C; S. 13 - 30
1. Verfasser:	Terrani, Kurt A.
Format:	Journal Article
Sprache:	Englisch
Veröffentlicht:	Amsterdam Elsevier B.V 01.04.2018 Elsevier BV Elsevier
Schlagworte:	Aluminum oxide Carbides Cladding Ferrites Light water reactors MATERIALS SCIENCE Metal matrix composites Motivation Nuclear engineering Nuclear fuels Nuclear reactors Nuclear safety Oxidation Oxidation resistance Safety margins Silicon Silicon carbide Zirconium
ISSN:	0022-3115, 1873-4820
Online-Zugang:	Volltext
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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.
AbstractList	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.
Author	Terrani, Kurt A.
Author_xml	– sequence: 1 givenname: Kurt A. surname: Terrani fullname: Terrani, Kurt A. email: terranika@ornl.gov organization: Oak Ridge National Laboratory, Oak Ridge, TN 37831, United States
BackLink	https://www.osti.gov/servlets/purl/1471930$$D View this record in Osti.gov
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Snippet	The motivation for transitioning away from zirconium-based fuel cladding in light water reactors to significantly more oxidation-resistant materials, thereby...
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SubjectTerms	Aluminum oxide Carbides Cladding Ferrites Light water reactors MATERIALS SCIENCE Metal matrix composites Motivation Nuclear engineering Nuclear fuels Nuclear reactors Nuclear safety Oxidation Oxidation resistance Safety margins Silicon Silicon carbide Zirconium
Title	Accident tolerant fuel cladding development: Promise, status, and challenges
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