Optimization of TOFD Detection for Thick-Walled Nuclear Pressure Vessel with Inner Surface Defect

DAI Zhen; WANG Xin; JING Shangqian; LI Wei; HAO Xiaojun; WANG Lei

Volume 35 Issue 2

Feb. 2025

Turn off MathJax

Article Contents

Abstract

References

Article Navigation > Nuclear Power Engineering > 2014 > 35(2): 79-83

DAI Zhen, WANG Xin, JING Shangqian, LI Wei, HAO Xiaojun, WANG Lei. Optimization of TOFD Detection for Thick-Walled Nuclear Pressure Vessel with Inner Surface Defect[J]. Nuclear Power Engineering, 2014, 35(2): 79-83.

Citation:

DAI Zhen, WANG Xin, JING Shangqian, LI Wei, HAO Xiaojun, WANG Lei. Optimization of TOFD Detection for Thick-Walled Nuclear Pressure Vessel with Inner Surface Defect[J]. Nuclear Power Engineering, 2014, 35(2): 79-83.

Citation:

PDF( 846 KB)

Optimization of TOFD Detection for Thick-Walled Nuclear Pressure Vessel with Inner Surface Defect

1. Institute of Materials Science and Engineering, Ocean University of China, Qingdao, Shangdong, 266100, China;
2. Guodian Science and Technology Research Institute, Nanjing, 210031, China;
3. Hebei Electric Power Research Institute, Shijiazhuang, 050021, China

Received Date: 2013-01-09
Rev Recd Date: 2013-10-25

Available Online: 2025-02-15

Abstract

Abstract

The 20° probe is proposed in order to optimize the TOFD detection. Acoustic wave characteristics, detection signal and image feature of 20° probe are analyzed. The optimal frequency is determined by comparing 2.25MHz and 5MHz. Through TOFD detection of artificial inner surface defect, the optimum detections are demonstrated, which are fit for detecting thick-walled nuclear pressure vessel with inner surface defect. The experimental results show that:（a） for thick-walled nuclear pressure vessel with inner surface detect, 20° probe and 5MHz frequency are optimization.（b） By this optimization detection, artificial inner surface defect with height of 2mm can be effectively distinguished in nuclear pressure vessel with thickness of 120mm.
- TOFD,
- Detection optimization,
- Thick-walled,
- Pressure vessel,
- Fine grain material,
- Inner surface defect

FullText(HTML)

References(0)

References

Relative Articles

[1]	Chen Peng, Zhu Yizhou, Zhang Kai, Xie Yongcheng. Dynamic Reliability Analysis of CRDM Pressure Shell under Multiple Failure Modes[J]. Nuclear Power Engineering, 2023, 44(1): 118-123. doi: 10.13832/j.jnpe.2023.01.0118
[2]	Cao Huasong, Sun Peiwei. Research on Fault Detection and Identification Method of Small PWR Based on Principal Component Analysis[J]. Nuclear Power Engineering, 2022, 43(1): 148-155. doi: 10.13832/j.jnpe.2022.01.0148
[3]	Zhao Yanyi, Wang Zewu, Li Junbao. Study on Dynamical Stress Characteristics of DVI Nozzle Subjected to Pressurized Thermal Shocks[J]. Nuclear Power Engineering, 2022, 43(4): 78-85. doi: 10.13832/j.jnpe.2022.04.0078
[4]	Hu Chenxu, Sun Jiawei, Li Bingqian. Research on PA Ultrasonic Inspection Technology in RPV[J]. Nuclear Power Engineering, 2021, 42(2): 148-152. doi: 10.13832/j.jnpe.2021.02.0148
[5]	Huang Sanao, Li Ming, Xu Ke, Shi Yingjie. Surface Defect Detection on Nuclear Power Plant Components Based on Photometric Stereo under Near-Field LED Light[J]. Nuclear Power Engineering, 2021, 42(4): 191-197. doi: 10.13832/j.jnpe.2021.04.0191
[6]	Xu Jiangming, Ke Liming. Characteristic Extraction Based on Wavelet Packet and Pattern Recognition for Ultrasonic Inspection Signals from Defects in FSW Joints Using Artificial Neural Network[J]. Nuclear Power Engineering, 2020, 41(1): 163-166. doi: 10.13832/j.jnpe.2020.01.0163
[7]	Xie Honghu, Zhang Feng, Qin Junwei, Chen Chuyuan. Optimum Design of Personnel Airlock Pneumatic Circuit and Improvement of Tightness Detection Procedure for Nuclear Power Plants[J]. Nuclear Power Engineering, 2019, 40(2): 120-122. doi: 10.13832/j.jnpe.2019.02.0120
[8]	Wang Yongchao, Fan Kai, JIang Shenghan, Zhang Bin, CAo Qi, LI Yun, Feng Weiwei. Development of Detection Device Pressure Vessel for Control Rod Position Sensor in Nuclear Power Plants[J]. Nuclear Power Engineering, 2017, 38(S2): 160-163. doi: 10.13832/j.jnpe.2017.S2.0160
[9]	Shao Zhen, Cheng Xiaowen, Le Yu. Analysis and Treatment of Weld Defects in Negative Pressure Cavity Valve of Main Pipeline in Nuclear Reactor[J]. Nuclear Power Engineering, 2017, 38(S2): 100-103. doi: 10.13832/j.jnpe.2017.S2.0100
[10]	LÜ Li, Yu Tao, Yu Hongxing, Wu Dan, Xie Jinsen, Peng Huanhuan. Research on Wall-to-Vapor Convective Heat Transfer Model in Reflooding Phase of Typical PWR Based on RELAP5[J]. Nuclear Power Engineering, 2015, 36(2): 42-45. doi: 10.13832/j.jnpe.2015.02.0042
[11]	Qin Mian, Yu Tao, Yu Deyong, Li Zhifeng, Lu Li. Transient Numerical Investigation of Direct Vessel Injection for AP1000 under Pressurized Thermal Shock[J]. Nuclear Power Engineering, 2015, 36(1): 1-8. doi: 10.13832/j.jnpe.2015.01.0001
[12]	ZHANG Lin, CHU Qibao, FANG Yonggang. Nuclear Safety Review on Exceeding Allowable Flaw Treatment of Reactor Pressure Vessel[J]. Nuclear Power Engineering, 2014, 35(2): 84-85,97.
[13]	ZhOu Zhou, Meng Shaopeng, Bao Jie. Study on Fatigue of Reactor Coolant Piping and Minimum Piping Wall Thickness[J]. Nuclear Power Engineering, 2014, 35(3): 46-50. doi: 10.13832/j.jnpe.2014.03.0046
[14]	ZHANG Guo-feng, ZHANG Bao-jun, YAN Zhi, JIN De-rong. Study on Ultrasonic Inspection Technology for Reactor Pressure Vessel Stud[J]. Nuclear Power Engineering, 2013, 34(4): 143-146.
[15]	LIU Zhi-wei, QIAO Hong-wei, ZHANG Yong. Analysis of Probabilistic Fracture Mechanics for PTS of Reactor Pressure Vessel[J]. Nuclear Power Engineering, 2013, 34(5): 37-40,44.
[16]	MA Na, YIN Chang-geng, QIN Jin-guang. Wall Thinning Analysis of Carbon Steel Pipes in Nuclear Power Plants[J]. Nuclear Power Engineering, 2013, 34(2): 123-125.
[17]	ZHENG Bin, ZANG Fenggang, SUN Yingxue. Pressurized Thermal Shock Analysis for Reactor Pressure Vessels[J]. Nuclear Power Engineering, 2012, 33(1): 1-3,13.
[18]	BAI Wenting, DAI Junwu, FENG Guozhong, RONG Feng. Contrast of Aseismic Design for NPP Pressure Pipelines of Class 2[J]. Nuclear Power Engineering, 2011, 32(5): 59-63,68.
[19]	WANG Yongjiao, YANG Zhipeng. Analysis and Treatment of Cladding Layer Defects on Outlet Nozzle of Reactor Pressure Vessel[J]. Nuclear Power Engineering, 2011, 32(4): 83-85.
[20]	ZHANG Tian-yi, WAN Li, SHI Li, ZHANG Chuan-yong. FE Simulation of Bolt-up Process for Press-Retraining Bolts of HTR-PM Pressure Vessel[J]. Nuclear Power Engineering, 2011, 32(S1): 54-56.