Research on Unloading Instruction Design Technology of Diesel Generators in HPR1000 Nuclear Power Plant

Wang Lin; Wu Qiaofeng; He Zhengxi; Liu Hongchun; Sun Shiyan; Li Yu; Chen Peng; Zhang Junqi

doi:10.13832/j.jnpe.2023.S2.0092

Volume 44 Issue S2

Dec. 2023

Turn off MathJax

Article Contents

Article Navigation > Nuclear Power Engineering > 2023 > 44(S2): 92-97

Wang Lin, Wu Qiaofeng, He Zhengxi, Liu Hongchun, Sun Shiyan, Li Yu, Chen Peng, Zhang Junqi. Research on Unloading Instruction Design Technology of Diesel Generators in HPR1000 Nuclear Power Plant[J]. Nuclear Power Engineering, 2023, 44(S2): 92-97. doi: 10.13832/j.jnpe.2023.S2.0092

Citation:

Wang Lin, Wu Qiaofeng, He Zhengxi, Liu Hongchun, Sun Shiyan, Li Yu, Chen Peng, Zhang Junqi. Research on Unloading Instruction Design Technology of Diesel Generators in HPR1000 Nuclear Power Plant[J]. Nuclear Power Engineering, 2023, 44(S2): 92-97. doi: 10.13832/j.jnpe.2023.S2.0092

Citation:

Wang Lin, Wu Qiaofeng, He Zhengxi, Liu Hongchun, Sun Shiyan, Li Yu, Chen Peng, Zhang Junqi. Research on Unloading Instruction Design Technology of Diesel Generators in HPR1000 Nuclear Power Plant[J]. Nuclear Power Engineering, 2023, 44(S2): 92-97. doi: 10.13832/j.jnpe.2023.S2.0092

PDF( 4420 KB)

Research on Unloading Instruction Design Technology of Diesel Generators in HPR1000 Nuclear Power Plant

doi: 10.13832/j.jnpe.2023.S2.0092

Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2023-07-11
Rev Recd Date: 2023-08-29
Publish Date: 2023-12-30

Abstract

Abstract

Engineered safety features actuation system is used to mitigate the consequences of accidents in nuclear power plants, which plays a vital role in the safety of nuclear power plants. The spurious triggering of unloading instruction of diesel generators may prevent the normal operation of engineered safety features. However, currently there are no clear design criteria and specific requirements for the mis-operation failure rate and mal-operation failure rate indicators for the unloading instruction of diesel generators. Therefore, an in-depth research on the design principles, reliability requirements and periodic test design of the unloading instruction of diesel generators is conducted based on the deterministic and probabilistic analysis. Then the design requirements for the unloading instruction of diesel generators are proposed, and the overall technical scheme for the unloading instruction of diesel generators is designed for the third generation nuclear power plant HPR1000. Finally, the fault tree and Markov reliability analysis methods are used for verification. The verification results show that the proposed design requirements are reasonable and the instruction design scheme has high reliability. This research provides an important reference for the design of subsequent nuclear power plant I&C system.
- Engineered safety features,
- Diesel generators,
- HPR1000,
- Fault tree,
- Markov

FullText(HTML)

References(10)

References

[1]	国家核安全局. 核动力厂设计安全规定: HAF 102-2016[S]. 北京: 国家核安全局,2016.
[2]	李哲. 核电厂丧失厂外电源事件下柴油发电机系统动态响应分析[J]. 核动力工程,2012, 33(1): 60-65. doi: 10.3969/j.issn.0258-0926.2012.01.013
[3]	国家质量技术监督局. 核电厂安全系统可靠性分析一般原则: GB/T 9225-1999[S]. 北京: 中国标准出版社,2004.
[4]	International Electrotechnical Commission. Functional safety of electrical/electronic/programmable electronic safety-related systems-part 2: requirements for electrical/electronic/programmable electronic safety-related systems: IEC 61508-2: 2010[S]. Geneva: International Electrotechnical Commission, 2010.
[5]	BECKMAN L. Easily assess complex safety loops[J]. Chemical Engineering Progress, 2001, 97(3): 57-59.
[6]	WANG X Y, HU M, ZHANG X Y, et al. Satellite reliability analysis based on dynamic fault tree[J]. Chinese Space Science and Technology, 2020, 40(6): 56-67.
[7]	MCNELLES P, ZENG Z C, RENGANATHAN G, et al. A comparison of fault trees and the dynamic flowgraph methodology for the analysis of FPGA-based safety systems part 1: reactor trip logic loop reliability analysis[J]. Reliability Engineering & System Safety, 2016, 153: 135-150.
[8]	BUKOWSKI J V, GOBLE W M. Using Markov models for safety analysis of programmable electronic systems[J]. ISA Transactions, 1995, 34(2): 193-198. doi: 10.1016/0019-0578(95)00008-N
[9]	威廉•戈布尔. 控制系统的安全评估与可靠性[M]. 白焰,董玲,杨国田,译. 北京: 中国电力出版社,2008: 84-88.
[10]	GUO H T, YANG X H. Automatic creation of Markov models for reliability assessment of safety instrumented systems[J]. Reliability Engineering & System Safety, 2008, 93(6): 829-837.