Performance analysis of irradiated thermo-mechanical coupled petal-shaped fuel rod under different power and heat transfer conditions

被引:0
|
作者
He, Binxian [1 ,2 ]
Zhang, Wenchao [1 ,2 ,3 ]
Meng, Xiangfei [4 ]
Sun, Jianchuang [1 ,2 ]
Du, Lipeng [1 ,2 ]
Cai, Weihua [1 ,2 ]
机构
[1] Northeast Elect Power Univ, Lab Thermofluid Sci & Nucl Engn, Jilin 132012, Peoples R China
[2] Northeast Elect Power Univ, Engn, Jilin 132012, Peoples R China
[3] Tsinghua Univ, Key Lab Adv Reactor Engn & Safety, Minist Educ, Beijing 100084, Peoples R China
[4] China Nucl Power Technol Res Inst Co Ltd, Shenzhen 518031, Peoples R China
基金
中国国家自然科学基金;
关键词
THERMAL-HYDRAULICS;
D O I
10.1016/j.nucengdes.2023.112732
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
As a new type of fuel rod, petal -shaped fuel rod (PSFR) has the advantages of lowering the core temperature and increasing the power density, and thus has a application prospect. Based on the thermal elastic-plastic theory, this paper establishes an analytical model for irradiated thermal-mechanical coupling performance of PSFR by user subroutine. Through numerical simulations of the full -cycle operation of PSFR under different power and heat transfer conditions, the performance parameters of fuel rods, such as fuel rod temperature and stress, are obtained, and their spatial distribution and the variation pattern with the operation time analyzed. The results show that increasing line power leads to a simultaneous increase in fuel rod temperature, stress, maximum deformation, and creep. However, appropriate reduction in heat transfer coefficient decreases the cladding stresses. The above research results will provide an essential theoretical basis for determining new PSFR's deformation and operation risk.
引用
收藏
页数:8
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