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contributor authorDeng, Yangbin
contributor authorWu, Yingwei
contributor authorZhang, Dalin
contributor authorTian, Wenxi
contributor authorSu, G. H.
contributor authorQiu, Suizheng
date accessioned2019-03-17T09:41:35Z
date available2019-03-17T09:41:35Z
date copyright1/24/2019 12:00:00 AM
date issued2019
identifier issn2332-8983
identifier otherners_005_01_011015.pdf
identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4255624
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.
publisherThe American Society of Mechanical Engineers (ASME)
titleSimulation on Pellet–Cladding Mechanical Interaction of Accident Tolerant Fuel With Coated Cladding
typeJournal Paper
journal volume5
journal issue1
journal titleJournal of Nuclear Engineering and Radiation Science
identifier doi10.1115/1.4041194
journal fristpage11015
journal lastpage011015-8
treeJournal of Nuclear Engineering and Radiation Science:;2019:;volume( 005 ):;issue: 001
contenttypeFulltext


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