Multiphysics Modeling of Pressurized Water Reactor Fuel Performance

被引:1
|
作者
Wang Zhu [1 ]
Zhang Chungyu [2 ]
Yuan Cenxi [2 ]
机构
[1] Sun Yat Sen Univ, Sch Phys, Guangzhou 510275, Guangdong, Peoples R China
[2] Sun Yat Sen Univ, Sinofrench Inst Nucl Engn & Technol, Zhuhai 519082, Peoples R China
关键词
multiphysics simulation; pressurized water reactor; fuel rod;
D O I
10.1115/1.4039848
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Nuclear 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.
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收藏
页数:8
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