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dc.contributor.authorMao, Jianfeng
dc.contributor.authorBao, Shiyi
dc.contributor.authorLu, Zhiming
dc.contributor.authorLuo, Lijia
dc.contributor.authorGao, Zengliang
dc.date.accessioned2019-02-28T11:05:33Z
dc.date.available2019-02-28T11:05:33Z
dc.date.copyright9/10/2018 12:00:00 AM
dc.date.issued2018
dc.identifier.issn2332-8983
dc.identifier.otherners_004_04_041015.pdf
dc.identifier.urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4252588
dc.description.abstractThe so-called in-vessel retention (IVR) was considered as a severe accident management strategy and had been certified by Nuclear Regulatory Commission (NRC) in U.S. as a standard measure for severe accident management since 1996. In the core meltdown accident, the reactor pressure vessel (RPV) integrity should be ensured during the prescribed time of 72 h. However, in traditional concept of IVR, several factors that affect the RPV failure were not considered in the structural safety assessment, including the effect of corium crust on the RPV failure. Actually, the crust strength is of significant importance in the context of a severe reactor accident in which molten core material melts through the reactor vessel and collects on the lower head (LH) of the RPV. Consequently, the RPV integrity is significantly influenced by the crust. A strong, coherent crust anchored to the RPV walls could allow the yet-molten corium to fall away from the crust as it erodes the RPV, therefore thermally decoupling the melt pool from the coolant and sharply reducing the cooling rate. Due to the thermal resistance of the crust layer, it somewhat prevents further attack of melt pool from the RPV. In the present study, the effect of crust on RPV structural behaviors was examined under multilayered crust formation conditions with consideration of detailed thermal characteristics, such as high-temperature gradient across the wall thickness. Thereafter, systematic finite element analyses and subsequent damage evaluation with varying parameters were performed on a representative RPV to figure out the possibility of high temperature induced failures with the effect of crust layer.
dc.publisherThe American Society of Mechanical Engineers (ASME)
dc.titleThe Influence of Crust Layer on Reactor Pressure Vessel Failure Under Pressurized Core Meltdown Accident
dc.typeJournal Paper
dc.journal.volume4
dc.journal.issue4
dc.journal.titleJournal of Nuclear Engineering and Radiation Science
dc.identifier.doi10.1115/1.4040494
dc.journal.fristpage41015
dc.journal.lastpage041015-9
dc.treeJournal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 004
dc.contenttypeFulltext


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