Failure probability evaluation for a weld of the heat pipe in the Mega-Power heat pipe cooled reactor

被引：0

作者：

Xu, Xinyan ^{[1
]}

Liang, Qingzhu ^{[1
]}

Peng, Changhong ^{[1
]}

机构：

[1] School of Nuclear Science and Technology, University of Science and Technology of China, No.96, Jinzhai Road, Baohe District, Hefei,230026, China

来源：

Annals of Nuclear Energy | 2022年 / 177卷

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学科分类号：

摘要：

Codes (symbols) - Cracks - Creep - Fracture - Fracture mechanics - High temperature corrosion - Nuclear fuels - Outages - Residual stresses - Stress corrosion cracking - Thermal fatigue - Uncertainty analysis - Welds

引用

共 2 条

[1] Development of Code for Steady-State Thermal-Hydraulic Analysis in Bimodal Space Nuclear Reactor with Heat Pipe
State Key Laboratory of Intense Pulsed Radiation Simulation and Effect, Northwest Institute of Nuclear Technology, Xi'an
710024, China
Hedongli Gongcheng, 1600, 5 (34-39):
[2] Experimental Study on Heat Dissipation Characteristics of Flat Heat Pipe with Temperature-Controlled Phase Change Material Applied to High-Power T/R Module
He, Junjie
Wang, Yaoting
Meng, Tong
Wang, Qiuwang
Chu, Wenxiao
Hsi-An Chiao Tung Ta Hsueh/Journal of Xi'an Jiaotong University, 2022, 56 (06): : 142 - 150

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