Technology Improvement for Reactor Pressure Vessel of Ling’ao Phase II Nuclear Power Station, Shenzhen, Guangdong, 518124, China

CHEN Zhenwei; WU Chaorong; GUAN Jianwei; XING Rujun; YANG Chunle; GUAN Chunxiang

doi:10.13832/j.jnpe.2015.01.0068

Volume 36 Issue 1

Feb. 2025

Turn off MathJax

Article Contents

Abstract

References

Article Navigation > Nuclear Power Engineering > 2015 > 36(1): 68-71

CHEN Zhenwei, WU Chaorong, GUAN Jianwei, XING Rujun, YANG Chunle, GUAN Chunxiang. Technology Improvement for Reactor Pressure Vessel of Ling’ao Phase II Nuclear Power Station, Shenzhen, Guangdong, 518124, China[J]. Nuclear Power Engineering, 2015, 36(1): 68-71. doi: 10.13832/j.jnpe.2015.01.0068

Citation:

CHEN Zhenwei, WU Chaorong, GUAN Jianwei, XING Rujun, YANG Chunle, GUAN Chunxiang. Technology Improvement for Reactor Pressure Vessel of Ling’ao Phase II Nuclear Power Station, Shenzhen, Guangdong, 518124, China[J]. Nuclear Power Engineering, 2015, 36(1): 68-71. doi: 10.13832/j.jnpe.2015.01.0068

Citation:

CHEN Zhenwei, WU Chaorong, GUAN Jianwei, XING Rujun, YANG Chunle, GUAN Chunxiang. Technology Improvement for Reactor Pressure Vessel of Ling’ao Phase II Nuclear Power Station, Shenzhen, Guangdong, 518124, China[J]. Nuclear Power Engineering, 2015, 36(1): 68-71. doi: 10.13832/j.jnpe.2015.01.0068

PDF( 188 KB)

Technology Improvement for Reactor Pressure Vessel of Ling’ao Phase II Nuclear Power Station, Shenzhen, Guangdong, 518124, China

doi: 10.13832/j.jnpe.2015.01.0068

1. China Nuclear Power Engineering CO., Ltd., Shenzhen, Guangdong, 518124, China;
2. China Nuclear Power Technology Research Institute, Shenzhen, Guangdong, 518124, China

Received Date: 2014-01-16
Rev Recd Date: 2014-07-11

Available Online: 2025-02-15

Abstract

Abstract

The technology improvement for the reactor pressure vessel on Ling’ao Phase II Nuclear Power Station is given. This paper presents the description of the integrated core shell, integral reactor pressure vessel top cover, the control of irradiation sensitivity element content, co resident content reduction, the improvement of radial support blocks material and the increase the quantity of irradiation surveillance program capsules. The advantage of these improvement and impacts on equipment performance, construction, operation and maintenance of Ling’ao Phase II Nuclear Power Station is analyzed.
- Nuclear power station,
- RPV,
- Technology improvement

FullText(HTML)

References(0)

References

Relative Articles

[1]	Dong Yuanyuan, Zhang Yabin, Du Hua, Wang Xuxin, Zhao Wei. Study on Cyclic Relaxation Characteristics of C-ring for Reactor Pressure Vessel[J]. Nuclear Power Engineering, 2022, 43(4): 65-69. doi: 10.13832/j.jnpe.2022.04.0065
[2]	Yu Peng, Yang Xiaoming, Ma Rubing, Yuan Yidan. Study on Modified θ-projection Creep Model of Reactor Pressure Vessel Steel SA533B[J]. Nuclear Power Engineering, 2022, 43(4): 86-90. doi: 10.13832/j.jnpe.2022.04.0086
[3]	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
[4]	Jiang Xing, Weng Yu, Wang Haijun. Study on Heat Distribution Characteristics of Direct Safety Injection of Reactor Pressure Vessel[J]. Nuclear Power Engineering, 2021, 42(5): 119-122. doi: 10.13832/j.jnpe.2021.05.0119
[5]	Zhang Qi, Cao Guanghui, Geng Yan, Kong Jing, Liu Peng, Chen Zixi. Analysis of Effectiveness of Medium Voltage Mobile Power Supplies in M310 and Modified Nuclear Power Plants[J]. Nuclear Power Engineering, 2019, 40(4): 81-84.
[6]	Zhu Guangqiang, Wei Yanhui. Status Assessment of RPV Irradiation Embrittlement[J]. Nuclear Power Engineering, 2018, 39(4): 39-42. doi: 10.13832/j.jnpe.2018.04.0039
[7]	Wang Xiaobing, Long Tao, Fan Yijun, Wen Xiaojun. Optimization Analysis about Pre-Tightening Technology of Stud for Reactor Pressure Vessels[J]. Nuclear Power Engineering, 2018, 39(6): 64-68. doi: 10.13832/j.jnpe.2018.06.0064
[8]	Yao Chong. Analysis and Improvement of Small Branch Pipe Leakage of Reactor Coolant in Nuclear Power Plant[J]. Nuclear Power Engineering, 2018, 39(S1): 94-97. doi: 10.13832/j.jnpe.2018.S1.0094
[9]	Li Chengliang, Li Yuanfei, MO Huajun, Liu Feihua, Chen Jun, SHu Guogang. Irradiation Damage Effects on Microstructure of Reactor Pressure Vessel Steels[J]. Nuclear Power Engineering, 2017, 38(S1): 54-57. doi: 10.13832/j.jnpe.2017.S1.0054
[10]	Hong Maocheng, Yu Zhe, Lin Ge, Xiao Xuezhu, Ma Guanbing. Calculations and Simulation of Ultrasonic Inaccessible Zones for Outlet to Shell Weld in RPV[J]. Nuclear Power Engineering, 2015, 36(4): 118-121. doi: 10.13832/j.jnpe.2015.04.0118
[11]	Nie Zhiping, Wang Nianwei, Dong Wanfu. Analysis and Processing of Main Bolt Gluing in RPV[J]. Nuclear Power Engineering, 2015, 36(2): 109-112. doi: 10.13832/j.jnpe.2015.02.0109
[12]	Jiang Guofu, Li Guoyun, Luan Xingfeng, Zhang Haisheng, Huang Juan, Yang Xu, Cao Jiebao, Sun Kai. Irradiation Surveillance of RPV for Unit 1＆2 of QinshanⅡNPP[J]. Nuclear Power Engineering, 2015, 36(S1): 187-190. doi: 10.13832/j.jnpe.2015.S1.0187
[13]	Yang Guodong. Technology Improvement for Pipeline Anticorrosion of Sea Water Cooling System in Qinshan Nuclear Power Plant[J]. Nuclear Power Engineering, 2014, 35(S1): 189-191.
[14]	ZHANG Li-ping, ZHENG Lian-gang, LU Yue-chuan, LIU Wen-jin. Analysis of Fast Fracture of Core Region of RPV[J]. Nuclear Power Engineering, 2013, 34(5): 30-32.
[15]	DANG Ying, WEN Yao-ceng, QIU Shao-yu, CHEN Yong, LUO Qiang, LI Chuan-qian. Study on Performance of Novel Overlaying Welding Materials on the Sealing Face of RPV[J]. Nuclear Power Engineering, 2013, 34(5): 84-88.
[16]	LIU Jinhua, WEN Yan, ZHANG Xuemei, HUO Songmin, GONG Bin, HE Yanchun. Corrosion Properties of Sealing Surface Material for RPV under Abnormal Working Conditions[J]. Nuclear Power Engineering, 2012, 33(1): 83-87.
[17]	XIONG Guangming, DUAN Yuangang, DENG Xiaoyun, TAN Yu, JIN Ting, YANG Nengren. Numerical Simulation Research on C-ring of CPR1000 Reactor Pressure Vessel[J]. Nuclear Power Engineering, 2012, 33(6): 9-12.
[18]	ZHU Zheng-qing. Research and Development of Modern Large-Scale Reactor Pressure Vessel Materials[J]. Nuclear Power Engineering, 2011, 32(S2): 1-4,8.
[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]	TAN Xiao-hui. Effect of Fabrication Error of Reactor Pressure Vessel on Its Load-Bearing Ability[J]. Nuclear Power Engineering, 2011, 32(S1): 201-204.