Study on Earthquake Interaction between Safety-Related and Non-Safety- Related Items in Equipment Cooling Water System Room of Qinshan Nuclear Power Plant

Tan Yong; Zhang Liang; Peng Jun; Zhang Wangchao; Zhou Wentao; Qu Ting; Xu Gang; Wang Yue

doi:10.13832/j.jnpe.2022.S1.0080

Volume 43 Issue S1

Jul. 2022

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Article Navigation > Nuclear Power Engineering > 2022 > 43(S1): 80-85

Tan Yong, Zhang Liang, Peng Jun, Zhang Wangchao, Zhou Wentao, Qu Ting, Xu Gang, Wang Yue. Study on Earthquake Interaction between Safety-Related and Non-Safety- Related Items in Equipment Cooling Water System Room of Qinshan Nuclear Power Plant[J]. Nuclear Power Engineering, 2022, 43(S1): 80-85. doi: 10.13832/j.jnpe.2022.S1.0080

Citation:

Tan Yong, Zhang Liang, Peng Jun, Zhang Wangchao, Zhou Wentao, Qu Ting, Xu Gang, Wang Yue. Study on Earthquake Interaction between Safety-Related and Non-Safety- Related Items in Equipment Cooling Water System Room of Qinshan Nuclear Power Plant[J]. Nuclear Power Engineering, 2022, 43(S1): 80-85. doi: 10.13832/j.jnpe.2022.S1.0080

Citation:

Tan Yong, Zhang Liang, Peng Jun, Zhang Wangchao, Zhou Wentao, Qu Ting, Xu Gang, Wang Yue. Study on Earthquake Interaction between Safety-Related and Non-Safety- Related Items in Equipment Cooling Water System Room of Qinshan Nuclear Power Plant[J]. Nuclear Power Engineering, 2022, 43(S1): 80-85. doi: 10.13832/j.jnpe.2022.S1.0080

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Study on Earthquake Interaction between Safety-Related and Non-Safety- Related Items in Equipment Cooling Water System Room of Qinshan Nuclear Power Plant

doi: 10.13832/j.jnpe.2022.S1.0080

1.
CNNP Nuclear Power Operations Management Co., Ltd., Haiyan, Zhenjiang, 314300, China
2.
Shanghai Nuclear Engineering Research & Design Institute Co., Ltd., Shanghai, 200233, China
3.
Second Nuclear Power Division of National Nuclear Safety Administration, Beijing, 100032, China
4.
Shanghai Jiaotong University, Shanghai, 200240, China

Received Date: 2022-01-18
Rev Recd Date: 2022-04-24
Publish Date: 2022-06-15

Abstract

Abstract

In order to solve the problems of mixed arrangement of safety-related and non-safety-related items in the equipment cooling water system room of Qinshan Nuclear Power Plant and possible interaction under seismic conditions, by using the method of test and analysis, the safety-related valves and pipes arranged in the equipment cooling water system room are studied and analyzed under the influence of other non-safety-related ducts and pipes under seismic conditions. In the test, the size and height of the items in the equipment cooling water system room of Qinshan Nuclear Power Plant are reproduced 1:1, and the tests are carried out through various interactive methods such as flat fall, single pendulum, and dumping. Taking the pressure retaining performance of pipes and valves as the failure criterion, the deformation and impact acceleration are measured and analyzed. In order to verify the reliability of the test, the numerical simulation method is used to analyze and compare the failure of the duct-pipe interaction conditions, and the results are consistent with the test method. The final research results show that the non-safety-related items such as the duct arranged at 3.6 m above the top of the equipment cooling water system room and the DN50 pipe arranged at 8 m above the top of the equipment cooling water system room in Qinshan Nuclear Power Plant will not damage the function and structural integrity of the safety-related equipment cooling water system header and valve below.
- Earthquake,
- Interaction,
- Integrity,
- Equipment cooling water system,
- Pipe,
- Valve

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References(10)

References

[1]	国家质量技术监督局. 核电厂安全重要系统和部件的实体防护: GB/T 13285—1999[S]. 北京: 中国标准出版社, 2004: 4-17.
[2]	International Atomic Energy Agency. Earthquake experience and seismic qualification by indirect methods in nuclear installations: IAEA-TECDOC-1333[R]. Vienna: IAEA, 2003.
[3]	JOHNSON J J, GÜRPINAR A, CAMPBELL R D, et al. Seismic design standards and calculational methods in the United States and Japan: NUREG/CR-7230[R]. Washington: U. S. Nuclear Regulatory Commission, 2013
[4]	STEVENSON J D. Application of bounding spectra to seismic design of piping based on the performance of above ground piping in power plants subjected to strong motion earthquakes: NUREG/CR-6240[R]. Washington: U. S. Nuclear Regulatory Commission, 1995.
[5]	Stevenson and Associates. Procedure for seismic evaluation and design of small bore piping (NCIG-14): EPRI NP-6628[R]. Palo Alto: EPRI, 1990.
[6]	刘少华. 基于LS-DYNA的轿车保险杠耐撞性研究[D]. 长春: 吉林大学, 2008.
[7]	赵海鸥. LS-DYNA动力分析指南[M]. 北京: 兵器工业出版社, 2003, 244-249.
[8]	范亚夫,段祝平. Johnson-Cook材料模型参数的实验测定[J]. 力学与实践,2003, 25(5): 40-43. doi: 10.3969/j.issn.1000-0879.2003.05.013
[9]	董菲,GERMAIN G,LEBRUN J L,等. 有限元分析法确定Johson-Cook本构方程材料参数[J]. 上海交通大学学报,2011, 45(11): 1657-1660,1667.
[10]	Livermore Software Technology Corporation. LS-DYNA^® Keyword user’s manual volume II: material models[M]. Livermore: Livermore Software Technology Corporation, 2014, 89-95.