Design of Data Acquisition Method of Temperature Probe for Primary Circuit in Nuclear Power Plants

Liu Jianguang; Liu Ruhuan; Huang Yun

doi:10.13832/j.jnpe.2017.06.0057

Volume 38 Issue 6

Feb. 2025

Turn off MathJax

Article Contents

Abstract

References

Article Navigation > Nuclear Power Engineering > 2017 > 38(6): 57-60

Liu Jianguang, Liu Ruhuan, Huang Yun. Design of Data Acquisition Method of Temperature Probe for Primary Circuit in Nuclear Power Plants[J]. Nuclear Power Engineering, 2017, 38(6): 57-60. doi: 10.13832/j.jnpe.2017.06.0057

Citation:

Liu Jianguang, Liu Ruhuan, Huang Yun. Design of Data Acquisition Method of Temperature Probe for Primary Circuit in Nuclear Power Plants[J]. Nuclear Power Engineering, 2017, 38(6): 57-60. doi: 10.13832/j.jnpe.2017.06.0057

Citation:

PDF( 692 KB)

Design of Data Acquisition Method of Temperature Probe for Primary Circuit in Nuclear Power Plants

doi: 10.13832/j.jnpe.2017.06.0057

1. China Nuclear Power Engineering Co. Ltd., Shenzhen, Guangdong, 518124, China;
2. Liaoning Hong Yan He Nuclear Power Co. Ltd., Dalian, Liaoning, 116000, China

Received Date: 2016-12-23
Rev Recd Date: 2017-07-12

Available Online: 2025-02-09

Abstract

Abstract

The traditional data acquisition method for reactor coolant system temperature measurement channel calibration test（RCP63） is artificial acquisition method. It is with low processing efficiency, prone to human error, poor archiving and other issues. For these problems, this paper studies the DCS（digital instrument control system） data acquisition characteristics of nuclear power plants, and uses the database data in the DCS（digital instrument control system） for data acquisition. The method had been successfully applied to the unit 3 of Hongyanhe Nuclear Power Plant, which increased the work efficiency and reduced the potential human errors.
- Temperature measurement,
- Data collection,
- Cross-match

FullText(HTML)

References(0)

References

Relative Articles

[1]	Pu Ke, Song Houde, Liu Xiaojing, Song Meiqi. Prediction of Nuclear Power Plant Operating Parameters Based on Transfer Learning between Simulation and Measurement Data[J]. Nuclear Power Engineering, 2025, 46(2): 261-271. doi: 10.13832/j.jnpe.2024.080004
[2]	He Jinyu, Zhao Yang, Deng Rui, Wang Fanyu, Zhang Naixin. Research on the Test Equipment for Operational Characteristics of Control Rod Drive Mechanism[J]. Nuclear Power Engineering, 2025, 46(1): 273-278. doi: 10.13832/j.jnpe.2025.01.0273
[3]	Li Wei, Zhou Qiangqiang, Zhang Ji, Yan Guohua, Yu Zhaohui. Method and Device Development of Output Test for Pyrotechnic Actuator on Squib Valve in AP/CAP Nuclear Plant[J]. Nuclear Power Engineering, 2023, 44(1): 183-186. doi: 10.13832/j.jnpe.2023.01.0183
[4]	Xin Sufang, Wu Dan, Shen Yaou, Ren Chunming, Chen Shilong. Characterization Analysis of Core Outlet Temperature Measurement in Nuclear Power Plants[J]. Nuclear Power Engineering, 2023, 44(3): 237-242. doi: 10.13832/j.jnpe.2023.03.0237
[5]	Cai Wanrui, Zhang Zhongxiang, Wang Chao, Yin Jichao. Research on RTD Degradation Detection Algorithm Based on Cross-Comparison[J]. Nuclear Power Engineering, 2022, 43(S2): 47-52. doi: 10.13832/j.jnpe.2022.S2.0047
[6]	Li Weicai, Liu Pengliang, Wang Congzheng, Guo Yan. Research on Machine Vision Measurement Method of Rod Spacing Data for PWR Fuel after Irradiation[J]. Nuclear Power Engineering, 2022, 43(4): 53-59. doi: 10.13832/j.jnpe.2022.04.0053
[7]	Ma Xiaoyu, Deng Tao. Improvement and Test Verification of Reactor-Core Neutron and Temperature Detector[J]. Nuclear Power Engineering, 2021, 42(2): 105-109. doi: 10.13832/j.jnpe.2021.02.0105
[8]	Ren Chunming, Du Sijia, Deng Jian, Wu Qing, Xin Sufang, Hu Ying, Liu Xiaobo. Research on Hot Leg Temperature Mixing and Measurement Characteristics of Generation III Advanced Reactor[J]. Nuclear Power Engineering, 2021, 42(3): 203-207. doi: 10.13832/j.jnpe.2021.03.0203
[9]	Yuan Meichun, Sun Dongmei, Nan Xiayu. Research and Application of Calibration Test Method for PTR Liquid Level Gauge in EPR Units[J]. Nuclear Power Engineering, 2020, 41(5): 168-172.
[10]	Jiang Botao, Hines J. Wesley, Zhao Fuyu. Application of Ant Colony Optimization Least Squares Support Vector Machine in Measurement Data Fitting[J]. Nuclear Power Engineering, 2018, 39(6): 156-160. doi: 10.13832/j.jnpe.2018.06.0156
[11]	Zhang Qi. Research and Development of Service Life and Replacement Strategy for Neutron-temperature Measurement Channel[J]. Nuclear Power Engineering, 2017, 38(4): 120-122. doi: 10.13832/j.jnpe.2017.04.0120
[12]	Hu Zehua, Wang Jia, SHi Xueming, DenG Li, SuN Weili. Production of Thermal Scattering Law Data for H Bound in H₂O at Any Temperature[J]. Nuclear Power Engineering, 2017, 38(3): 34-37. doi: 10.13832/j.jnpe.2017.03.0034
[13]	Li Guangfeng, Li Shi, Zhang Mingliang. Fault Handling of Nuclear Power Plant PLC Data Acquisition System Based on MSG Instruction[J]. Nuclear Power Engineering, 2017, 38(2): 130-133. doi: 10.13832/j.jnpe.2017.02.0130
[14]	Shi Qing, Yang Jicheng, Su Wanhua, Wang Yan. Studies on Cross Connection between CEPR Auxiliary Power Supply Systems[J]. Nuclear Power Engineering, 2015, 36(S1): 47-50. doi: 10.13832/j.jnpe.2015.S1.0047
[15]	Chen Jing, Chen Ke, huo Yujia, Li Hongxia, Yu Junhui, Li Xiaofen. Method to Improve Measurement Accuracy for Bypass Temperature of Reactor Coolant System in Nuclear Power Plants[J]. Nuclear Power Engineering, 2015, 36(2): 93-95. doi: 10.13832/j.jnpe.2015.02.0093
[16]	huo Yujia, Li Hongxia, Li Liang, Chen Jing, Li Xiaofen, Zhu Jialiang. Study on Reactor Coolant Temperature Channel Calibration Test in Digital Control Nuclear Power Plants[J]. Nuclear Power Engineering, 2015, 36(2): 77-80. doi: 10.13832/j.jnpe.2015.02.0077
[17]	Hong Jingyan, Li Yiguo, Zhang Jinhua, PenG Dan, Wu Xiaobo, Hao Qian. Development of Computerized Reactor Start-up Instrument[J]. Nuclear Power Engineering, 2014, 35(S2): 218-220. doi: 10.13832/j.jnpe.2014.S2.0218
[18]	SHANG Jun-min, ZOU Lian-lie, YUAN Jian-zhong, ZHOU Yi, ZHAO Wei-dong. Heavy Water Reactor Pressure Tube Elongation Measurement and Data Analysis[J]. Nuclear Power Engineering, 2013, 34(2): 133-136.
[19]	DAI Hang-yang, DENG Sheng, CUI Can. Development of Digital Centralized Data Acquisition System for Reactors[J]. Nuclear Power Engineering, 2013, 34(2): 56-59.
[20]	ZOU Yang. Study on MCNP Related to Temperature-Dependent Neutron Cross Section Library Based on Different ENDF Format Databases[J]. Nuclear Power Engineering, 2012, 33(3): 12-16.