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dc.contributor.authorZhu, Wang
dc.contributor.authorChungyu, Zhang
dc.contributor.authorCenxi, Yuan
dc.date.accessioned2019-02-28T11:05:53Z
dc.date.available2019-02-28T11:05:53Z
dc.date.copyright5/16/2018 12:00:00 AM
dc.date.issued2018
dc.identifier.issn2332-8983
dc.identifier.otherners_004_03_031008.pdf
dc.identifier.urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4252646
dc.description.abstractNuclear fuel rods operate under complex radioactive, thermal, and mechanical conditions. Nowadays, fuel rod codes usually make great simplifications on analyzing the multiphysics behavior of fuel rods. The present study develops a three-dimensional (3D) module within the framework of a general-purpose finite element solver, i.e., abaqus, for modeling the major physics of the fuel rods. A typical fuel rod, subjected to stable operations and transient conditions, is modeled. The results show that the burnup levels have an important influence on the thermomechanical behavior of fuel rods. The swelling of fission products causes a dramatically increasing strain of pellets. The variation of the stress and the radial displacement of the cladding along the axial direction can be reasonably predicted. It is shown that a quick power ramp or a reactivity insertion accident can induce high tensile stress in the outer regime of the pellet and may cause further fragmentation to the pellets. Fission products migration effects and differential thermal expansion become more severe if there are flaws or imperfections on the pellet.
dc.publisherThe American Society of Mechanical Engineers (ASME)
dc.titleMultiphysics Modeling of Pressurized Water Reactor Fuel Performance
dc.typeJournal Paper
dc.journal.volume4
dc.journal.issue3
dc.journal.titleJournal of Nuclear Engineering and Radiation Science
dc.identifier.doi10.1115/1.4039848
dc.journal.fristpage31008
dc.journal.lastpage031008-8
dc.treeJournal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 003
dc.contenttypeFulltext


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