Failure Analysis for Wires of Coordinate Location Sensor for Control Rod in Reactors

ZHU Wei; WANG Fei; TANG Hongkui; ZHOU Yun; WEN Bang

Volume 33 Issue S2

Mar. 2025

Turn off MathJax

Article Contents

Abstract

References

Article Navigation > Nuclear Power Engineering > 2012 > 33(S2): 132-135

ZHU Wei, WANG Fei, TANG Hongkui, ZHOU Yun, WEN Bang. Failure Analysis for Wires of Coordinate Location Sensor for Control Rod in Reactors[J]. Nuclear Power Engineering, 2012, 33(S2): 132-135.

Citation:

ZHU Wei, WANG Fei, TANG Hongkui, ZHOU Yun, WEN Bang. Failure Analysis for Wires of Coordinate Location Sensor for Control Rod in Reactors[J]. Nuclear Power Engineering, 2012, 33(S2): 132-135.

ZHU Wei, WANG Fei, TANG Hongkui, ZHOU Yun, WEN Bang. Failure Analysis for Wires of Coordinate Location Sensor for Control Rod in Reactors[J]. Nuclear Power Engineering, 2012, 33(S2): 132-135.

Citation:

ZHU Wei, WANG Fei, TANG Hongkui, ZHOU Yun, WEN Bang. Failure Analysis for Wires of Coordinate Location Sensor for Control Rod in Reactors[J]. Nuclear Power Engineering, 2012, 33(S2): 132-135.

PDF( 1098 KB)

Failure Analysis for Wires of Coordinate Location Sensor for Control Rod in Reactors

First Sub-Institute of Nuclear Power Institute of China, Chengdu, 610005, China

Received Date: 2012-10-25
Rev Recd Date: 2012-11-25

Available Online: 2025-03-08

Abstract

Abstract

The coordinate location sensor of control rod of XX Nuclear Power Plant failed during operation.In order to analyze the reason,it is necessary to take apart of the coordinate location sensor.Each coordinate sensor has 12 wires and each wire has a V flexure at the same position.And one wire is fractured at the top of the V flexure.In order to study the fracture reason of the wire,the microstructures of fractured,flexural and normal wires were investigated by using scanning electron microscope（SEM）,energy dispersive X ray spectrometer（EDS）,and optical microscopy（OM）.The results indicate that the wires are stress corroded,and the grain boundary became rather weak in the high temperature and high pressure environment in the reactor.Finally the wire is broken at the top of the V flexure due to tensile stress which caused by the differential heat expansion coefficient of the material.
- Wire of coordinate location sensor,
- Brittle fracture,
- Residual stress,
- Tensile stress

FullText(HTML)

References(0)

References

Relative Articles

[1]	Chen Ling, Wang Xinming, Zhang Yongfa, Zhang Liming, Jiang Lizhi, Jiao Meng, Liu Xiaoya. Analysis of Thermal Stress and Fatigue Induced by Dryout Oscillation in Once Through Steam Generator[J]. Nuclear Power Engineering, 2023, 44(4): 121-127. doi: 10.13832/j.jnpe.2023.04.0121
[2]	Liu Zhenshun, Zhang Sheng, Mao Qing, Zheng Xiangyuan. Research on the Closure Effect of Circumferential Through-Wall Cracks in Stainless Steel Piping under Residual Stress[J]. Nuclear Power Engineering, 2023, 44(2): 152-158. doi: 10.13832/j.jnpe.2023.02.0152
[3]	Wang Yinglong, Xie Hao, Xiong Jinbiao, Yang Yiang, Cheng Xu. Research on Void Distribution Measurement of 5×5 Rod Bundle Channel Based on Wire Mesh Sensor[J]. Nuclear Power Engineering, 2022, 43(1): 84-91. doi: 10.13832/j.jnpe.2022.01.0084
[4]	Liu Linlin, Xu Yugen, Zhang Xiaoling, Yang Heng, Zhu Wanxia, Li Ronghui, Zhao Xin, Sun Lei, Li Pengzhou. Research on High-Temperature Resistant Strain Sensor Based on Fiber-Optic Fabry-Perot Structure[J]. Nuclear Power Engineering, 2022, 43(S1): 94-98. doi: 10.13832/j.jnpe.2022.S1.0094
[5]	Zhang Ruikai, Liu Pan, Tan Jianping, Li Yue, Wang Dasheng, Tu Shandong. Calculation of Stress Intensity Factor of External Surface Crack on the Nozzle of Steam Generator in Nuclear Power Plant[J]. Nuclear Power Engineering, 2022, 43(5): 138-146. doi: 10.13832/j.jnpe.2022.05.0138
[6]	Fu Qiang, Min Yuansheng, Liu Chuan, Li Meifu, Li Yuguang. Study of Residual Stress Distribution of Large Ring-type Dissimilar Metal Weld in Reactor Pressure Vessel[J]. Nuclear Power Engineering, 2022, 43(3): 123-128. doi: 10.13832/j.jnpe.2022.03.0123
[7]	Zhang Siyuan, Lu Tianyu, Zeng Hui, Xu Chun, Zhang Zhuo, Huang Qingyu, Zhang Yaoyi, Wang Yuanmei. Multi-Feature Fusion Multi-Step State Prediction of Nuclear Power Sensor Based on LSTM[J]. Nuclear Power Engineering, 2021, 42(4): 208-213. doi: 10.13832/j.jnpe.2021.04.0208
[8]	Zhu Shaomin, Xia Hong, Peng Binsen, Wang Yan, Wang Zhichao, Zhang Jiyu, Jiang Yingying. Condition Monitoring Model for Sensors of Reactor Coolant Pump Based on PCA[J]. Nuclear Power Engineering, 2020, 41(3): 170-176. doi: 10.13832/j.jnpe.2020.03.0170
[9]	Lin Bingchi, Xu Xiao, Jin Ting, Kong Xiaofei, Liu Pan, Lu Wenjie, Nie Zhaoyu. Analysis of Weld Residual Stress of J-Groove Weld in Penetrate Part[J]. Nuclear Power Engineering, 2020, 41(1): 70-74. doi: 10.13832/j.jnpe.2020.01.0070
[10]	Jiang Zhaoxiang, He Pan, Zeng Jie, Wang Lei, Wang Guangjin, Liu Caixue. Design and Application of Ultrasound Stress Wave Signal Bandpass Filter[J]. Nuclear Power Engineering, 2019, 40(6): 140-143. doi: 10.13832/j.jnpe.2019.06.0140
[11]	Chang Haijun, Hou Yanyan, Yang Xiaohua, Shen Mengling. Simulation Technology for Post Weld Heat Treatment of Steel Containers for Nuclear Power Plants[J]. Nuclear Power Engineering, 2019, 40(6): 77-81. doi: 10.13832/j.jnpe.2019.06.0077
[12]	Li Wei, Peng Minjun, Liu Yongkuo. Research on Condition Monitoring Technique of Sensors in NPPs Based on PCA[J]. Nuclear Power Engineering, 2018, 39(1): 136-139. doi: 10.13832/j.jnpe.2018.01.0136
[13]	Wang Shuyu, Feng Qijie, Wang Hong, Li Jian, Liu Yaoguang. Measurement of Radiated Aluminum Weld Residual Stress by Neutron Diffraction[J]. Nuclear Power Engineering, 2016, 37(5): 40-42. doi: 10.13832/j.jnpe.2016.05.0040
[14]	Gao Jianbo, Li Meijuan, Wei Guohai, Liu Xiaolong, Li Yuqing, Liu Yuntao, Chen Dongfeng. A Shielding Assembly for Residual Stress Measurement of Radioactive Monitoring Sample by Neutron Diffraction[J]. Nuclear Power Engineering, 2016, 37(3): 185-188. doi: 10.13832/j.jnpe.2016.03.0185
[15]	Zhang Shiwei, Chen Xuede, Zhang Yong, Sun Lei, Li Xihua. Analysis of Weld Overlay Residual Stress for Dissimilar Metal Welds in Qinshan Nuclear Power Plant[J]. Nuclear Power Engineering, 2016, 37(S2): 4-6. doi: 10.13832/j.jnpe.2016.S2.0004
[16]	Chen Liang, Pang Hua, Song Xiaoming, Liu Lili. Research on Stress Threshold of Stress Corrosion Cracking of Inconel 718 Alloy Hold-down Spring[J]. Nuclear Power Engineering, 2015, 36(S2): 97-101. doi: 10.13832/j.jnpe.2015.S2.0097
[17]	Zhang Tianyi, Zhang Zhenxing, hu Lina, Xu Yu. Effect of Tube Structural Style on Thermal Stress in CEFR Intermediate Heat Exchanger[J]. Nuclear Power Engineering, 2015, 36(5): 148-151. doi: 10.13832/j.jnpe.2015.05.0148
[18]	Ni Peng, Hui Hu, Wang Xiaodong, Lin Shaoxuan, Zhang Liyan, Chen Qingqi. Numerical Simulation of Hydraulically Expanded Tube-to-Tube Sheet Joints in Steam Generator[J]. Nuclear Power Engineering, 2015, 36(5): 204-207. doi: 10.13832/j.jnpe.2015.05.0204
[19]	YANG Min, LUO Ying, FU Qiang, LI Yuguang. Investigation of Welding Residual Stress in J-Weld between Reactor Pressure Vessel Head and Two Control Rod Drive Mechanism Nozzles Based on Mockup-to-Production Analysis Method[J]. Nuclear Power Engineering, 2015, 36(6): 75-78. doi: 10.13832/j.jnpe.2015.06.0075
[20]	YU Xiaofei, ZHANG Yixiong. Thermal Stratification and Fatigue Stress Analysis for Pressurizer Surge Line[J]. Nuclear Power Engineering, 2011, 32(1): 6-9,20.