Scaling Study for Experimental Test of Advanced Reactor Analysis of Passive Feature of Containment and Its Simulation Hierarchy

LI Shengqiang; LI Weihua; JIANG Shengyao

Volume 34 Issue 2

Apr. 2013

Turn off MathJax

Article Contents

Abstract

References

Article Navigation > Nuclear Power Engineering > 2013 > 34(2): 94-98

LI Shengqiang, LI Weihua, JIANG Shengyao. Scaling Study for Experimental Test of Advanced Reactor Analysis of Passive Feature of Containment and Its Simulation Hierarchy[J]. Nuclear Power Engineering, 2013, 34(2): 94-98.

Citation:

PDF( 335 KB)

Scaling Study for Experimental Test of Advanced Reactor Analysis of Passive Feature of Containment and Its Simulation Hierarchy

1. Institute of Nuclear and New Energy of Tsinghua University, Beijing, 100084, China;
2. Key Laboratory of Nuclear engineering and Safety of Ministry of Education, Beijing, 102201, China

Received Date: 2011-11-16
Rev Recd Date: 2012-02-20

Available Online: 2025-03-08

Publish Date: 2013-04-25

Abstract

Abstract

Different containment safety features are analyzed.Combined with the accident process analysis and physical model classification,a containment system analysis hierarchy,which can be applied to advanced containment system simulation and experimental verification,is built.Different physical models,experimental methodology,scaling criteria,PIRT,mathematical models and test process logic are included.It attempts to provide theoretical support and design reference for future containment system characteristics verification experiments.It is also applicable for the system simulation,including complex coupling of physical phenomena and processes.
- Containment,
- Scaling,
- Passive safety,
- Hierarchical Analysis

FullText(HTML)

References(0)

References

Relative Articles

[1]	Tian Jiaming, Wang Yueshe, Li Biao, Zou Lin. Simulation Study on Transport Characteristics of Radioactive Aerosol in Containment[J]. Nuclear Power Engineering, 2024, 45(2): 88-95. doi: 10.13832/j.jnpe.2024.02.0088
[2]	Wang Yuqing, Weng Yanyun, Ni Muyi, Deng Lilin, Tan Yi, Zhang Minghao. A Preliminary Study on Aerosol Transport Characteristics in Containment Based on DPM Method[J]. Nuclear Power Engineering, 2024, 45(6): 290-296. doi: 10.13832/j.jnpe.2024.06.0290
[3]	Wu Kuibo, Liang Zhaorui, Zhang Tengfei, Cao Qing, Song Yongjun, Xue Yu, Liu Junjie. Fast Determination of Containment Leakage Rate Based on Pressure Rise Monitoring[J]. Nuclear Power Engineering, 2023, 44(5): 110-115. doi: 10.13832/j.jnpe.2023.05.0110
[4]	Zhang Xueyan, Yang Jun, Wang Shiqi, Deng Chengcheng, Li Yuquan, Zhang Peng, He Dandan. Stage Progress and Analysis of International Standard Problem 51 “Open Test”[J]. Nuclear Power Engineering, 2022, 43(6): 15-23. doi: 10.13832/j.jnpe.2022.06.0015
[5]	Huang Jieqing, Wu Xiaotian, Wen Liang, Peng Yue. Research on Calculation Method of Containment Spray Coverage Rate Based on Monte Carlo Simulation Method[J]. Nuclear Power Engineering, 2022, 43(5): 176-180. doi: 10.13832/j.jnpe.2022.05.0176
[6]	Rong Hua, Jin Song, Gong Jinxin. Fragility Analysis of Nuclear Power Plant Containment under Near-site Vibration[J]. Nuclear Power Engineering, 2022, 43(2): 126-132. doi: 10.13832/j.jnpe.2022.02.0126
[7]	Peng Cheng, Deng Jian. Model Study on Hydrogen Stratification Behavior within a Containment[J]. Nuclear Power Engineering, 2021, 42(3): 155-160. doi: 10.13832/j.jnpe.2021.03.0155
[8]	Shen Dongming, He Rui, Zhang Ji. Study on Gas Relaxation Process in Leakage Rate Measurement Stage of Containment Test Based on Time Series Analysis Method[J]. Nuclear Power Engineering, 2021, 42(5): 178-181. doi: 10.13832/j.jnpe.2021.05.0178
[9]	Yang Lei, Wang Ying, Zeng Daidan, Xia Zhimin. Suitability Evaluation of Containment Thermal-Hydraulics Codes in Marine NPP Reactor Compartment Safety Analysis[J]. Nuclear Power Engineering, 2020, 41(3): 68-73. doi: 10.13832/j.jnpe.2020.02.0068
[10]	Shen Dongming, Cai Jiantao, He Rui, Huang Xiaoming. Data Reliability Analysis during Containment Leakage Test Based on Statistical Software R[J]. Nuclear Power Engineering, 2020, 41(5): 99-103.
[11]	Liu Yusheng, Xu Chao, Hu Jian, Zhuang Shaoxin, Fang Fangfang. Numerical Analysis of ACME Station Blackout Integral Effect Test with Relap[J]. Nuclear Power Engineering, 2019, 40(3): 98-102. doi: 10.13832/j.jnpe.2019.03.0097
[12]	Zhang Xiaohua, Li Feng, Zhang Yu, Wu Qing, Yu Na, Zhang Shu, Xian Lin. Study on Applicability of RELAP Code in PRS Analysis[J]. Nuclear Power Engineering, 2019, 40(6): 189-193. doi: 10.13832/j.jnpe.2019.06.0189
[13]	Zhao Xu, Wang Hongjin, Ding Haiming. Installation Technology for Weirs of Steel Containment Vessel in a Passive Pressure Water Reactor[J]. Nuclear Power Engineering, 2019, 40(2): 146-149. doi: 10.13832/j.jnpe.2019.02.0146
[14]	BAi Jinhua, Zhao Bo. Optimization of Design on Passive Containment Cooling System by using Relap5 Code[J]. Nuclear Power Engineering, 2017, 38(6): 14-17. doi: 10.13832/j.jnpe.2017.06.0014
[15]	Li Le, Li Cheng, Zhang Yajun, Zhu Mingliang. Preliminary Analysis of AP1000 PCCS and Its Enhanced Performance[J]. Nuclear Power Engineering, 2017, 38(1): 36-40. doi: 10.13832/j.jnpe.2017.01.0036
[16]	Zhang Xiangke, Ma Guolu. Construction of Double Containment of CEPR Reactor Building[J]. Nuclear Power Engineering, 2015, 36(S1): 71-74. doi: 10.13832/j.jnpe.2015.S1.0071
[17]	HE Rui, JIA Wutong, ZHAO Jian. Research on Weight of Volume for Leakage Measurement Probe during CTT[J]. Nuclear Power Engineering, 2015, 36(6): 101-104. doi: 10.13832/j.jnpe.2015.06.0101
[18]	Cai Jiantao, Ni Yongsheng, JiA Wutong. Containment Test in Area of High Latitude and Low Temperature[J]. Nuclear Power Engineering, 2014, 35(5): 101-105. doi: 10.13832/j.jnpe.2014.05.0101
[19]	LI Shengqiang, LI Weihua, JIANG Shengyao. Study on Source Term Evaluation Method in Simulation and Scaling for Containment during LOCA[J]. Nuclear Power Engineering, 2012, 33(3): 132-137.
[20]	HOU Gang-ling, CHEN Shu-hua, LI Dong-mei. Analysis of Structural Seismic Response of Nuclear Power Plant Concrete Containment Vessel with Isolating Devices[J]. Nuclear Power Engineering, 2011, 32(S1): 76-79.