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dc.contributor.authorDeng, Yangbin
dc.contributor.authorWu, Yingwei
dc.contributor.authorZhang, Dalin
dc.contributor.authorTian, Wenxi
dc.contributor.authorSu, G. H.
dc.contributor.authorQiu, Suizheng
dc.date.accessioned2019-03-17T09:41:35Z
dc.date.available2019-03-17T09:41:35Z
dc.date.copyright1/24/2019 12:00:00 AM
dc.date.issued2019
dc.identifier.issn2332-8983
dc.identifier.otherners_005_01_011015.pdf
dc.identifier.urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4255624
dc.description.abstractIn this study, based on the code Fuel ROd Behavior Analysis (FROBA), a thermal–mechanical analysis code initially developed for traditional UO2-Zr fuel elements by our research group, a modified version was developed to perform the fuel performance simulation of accident tolerant fuels (ATFs), named FROBA-ATF. Compared with initial version, the cladding could be divided into arbitrary number control volumes with different materials in the new code, so it can be used to perform the calculation for multilayer coatings. In addition, a new nonrigid pellet–cladding mechanical interaction (PCMI) calculation model was established in the new code. The FROBA-ATF code was used to predict PCMI performance of two kind fuels with coated claddings, including the internal surface coating and external surface coating. The calculation result indicates that because the coating surface was close to the inner surface of the cladding where also was the PCMI surface, the absolute value of the combine pressure of internal surface-coated cladding was substantial larger than that of the external surface-coated cladding, which might be harmful the coating behavior. However, the internal surface-coated mode can provide a protection for alloy due to the isolation from direct contact with fuel pellets, which can result in a much lower equivalent stress of zirconium body during the PCMI.
dc.publisherThe American Society of Mechanical Engineers (ASME)
dc.titleSimulation on Pellet–Cladding Mechanical Interaction of Accident Tolerant Fuel With Coated Cladding
dc.typeJournal Paper
dc.journal.volume5
dc.journal.issue1
dc.journal.titleJournal of Nuclear Engineering and Radiation Science
dc.identifier.doi10.1115/1.4041194
dc.journal.fristpage11015
dc.journal.lastpage011015-8
dc.treeJournal of Nuclear Engineering and Radiation Science:;2019:;volume( 005 ):;issue: 001
dc.contenttypeFulltext


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