Study on Transient Performance in Loss of Coolant Accident for AP1000 SFP

Duan Yongqiang; He Xun; Jing Futing; Cai Zhiyun; Yu Xiaoquan

doi:10.13832/j.jnpe.2019.01.0147

Volume 40 Issue 1

Feb. 2019

Turn off MathJax

Article Contents

Abstract

References

Article Navigation > Nuclear Power Engineering > 2019 > 40(1): 147-151

Duan Yongqiang, He Xun, Jing Futing, Cai Zhiyun, Yu Xiaoquan. Study on Transient Performance in Loss of Coolant Accident for AP1000 SFP[J]. Nuclear Power Engineering, 2019, 40(1): 147-151. doi: 10.13832/j.jnpe.2019.01.0147

Citation:

Duan Yongqiang, He Xun, Jing Futing, Cai Zhiyun, Yu Xiaoquan. Study on Transient Performance in Loss of Coolant Accident for AP1000 SFP[J]. Nuclear Power Engineering, 2019, 40(1): 147-151. doi: 10.13832/j.jnpe.2019.01.0147

Citation:

PDF( 0 KB)

Study on Transient Performance in Loss of Coolant Accident for AP1000 SFP

doi: 10.13832/j.jnpe.2019.01.0147

Publish Date: 2019-02-15

Abstract

Abstract

The coupled mathematical thermal equilibrium model for main equipment in the spent fuel pool (SFP) is established and the transient change of the temperature of SFP water in various loss of coolant accidents is studied based on AP1000 power plant. The results show that the fuel rods are exposed after 24h when the loss of coolant accident occurs during the unloading of the whole reactor, while the fuel rods are exposed after 213h when the loss of coolant accident occurs after the fuel loading operation. The results give a reference response time for the operator to take countermeasures for the loss of coolant accident for the spent fuel pool.
- Spent fuel pool,
- Decay heat,
- Temperature transient of SFP,
- AP1000

FullText(HTML)

References(0)

References

Relative Articles

[1]	Han Jie, Dong Shubiao, Zhang Hongsheng, Zhang Xian, Wang Ying. Research on Operation Optimization of AP1000 Boric Acid Makeup Subsystem[J]. Nuclear Power Engineering, 2024, 45(S1): 32-38. doi: 10.13832/j.jnpe.2024.S1.0032
[2]	Wang Zhixiao, Hu Jian, Peng Yue, Xie Enfei, Wan Qian. Research on Mobile Emergency Cooling System for Spent Fuel Pool in Nuclear Power Plant[J]. Nuclear Power Engineering, 2023, 44(6): 220-225. doi: 10.13832/j.jnpe.2023.06.0220
[3]	Yang Ning, Li Huaqi, Zhang Xinyi, Tian Xiaoyan, Zhang Qiang. Fine Calculation of Decay Heat Power in Xi’an Pulsed Reactor[J]. Nuclear Power Engineering, 2021, 42(6): 24-31. doi: 10.13832/j.jnpe.2021.06.0024
[4]	Zhɑnɡ Guohui, Song Hehang, Luo Zhiping. Design and Study of Backup Cooling Mode for Spent Fuel Pool of CPR1000 Unit[J]. Nuclear Power Engineering, 2021, 42(5): 240-244. doi: 10.13832/j.jnpe.2021.05.0240
[5]	Yang Zhiye, Li Tao, Wang Binyuan, Li Song, Zhao Mingshen. Research on Lower C Seal Cutting Technology for AP1000 Large Canned Pumps[J]. Nuclear Power Engineering, 2020, 41(5): 138-141.
[6]	Zhang Shipeng. Verification of Thermal Cooling Capacity for a Spent Fuel Pool Expansion in a 1000 MW PWR Nuclear Power Plant[J]. Nuclear Power Engineering, 2018, 39(S2): 180-184. doi: 10.13832/j.jnpe.2018.S2.0180
[7]	Hao Chen, Zhao Qiang, Li Fu, Yu Yan, Zhang Chunyan, Zhang Huiyan. Uncertainty Analysis of Advanced Pressurized Water Reactor Fuel Assembly[J]. Nuclear Power Engineering, 2016, 37(3): 173-180. doi: 10.13832/j.jnpe.2016.03.0173
[8]	YU Hong. Emergency Classification of Nuclear Power Plants with Wet Storage Spent Fuel[J]. Nuclear Power Engineering, 2016, 37(5): 58-62. doi: 10.13832/j.jnpe.2016.05.0058
[9]	Wang Haitao, Dan Jianqiang, Gou Junli, Zhang Bo. Safety Analysis of Spent Fuel Pool in Case of LOCA[J]. Nuclear Power Engineering, 2015, 36(4): 136-139. doi: 10.13832/j.jnpe.2015.04.0136
[10]	Qin Mian, Yu Tao, Yu Deyong, Li Zhifeng, Lu Li. Transient Numerical Investigation of Direct Vessel Injection for AP1000 under Pressurized Thermal Shock[J]. Nuclear Power Engineering, 2015, 36(1): 1-8. doi: 10.13832/j.jnpe.2015.01.0001
[11]	WU Hao, GAN Quan, LUO Qi, XIAO Sanping, LIU Yan, CHEN Shushan. Decay Heat Removal Performance Analysis of AP1000 Startup Feed Water during Non-LOCA Accident[J]. Nuclear Power Engineering, 2015, 36(6): 92-96. doi: 10.13832/j.jnpe.2015.06.0092
[12]	Zhang Zhongwei, Liang Guoxing. Safety Analysis of Loss of Cooling Accident for Typical Spent Fuel Pool[J]. Nuclear Power Engineering, 2015, 36(4): 149-153. doi: 10.13832/j.jnpe.2015.04.0149
[13]	Yao Zenghua. Review on Core Design of AP1000[J]. Nuclear Power Engineering, 2014, 35(S1): 75-79.
[14]	Liu Xiaoheng. Schedule Management of Nuclear Island Design of First Kind of AP1000 Unit[J]. Nuclear Power Engineering, 2014, 35(5): 182-184. doi: 10.13832/j.jnpe.2014.05.0182
[15]	Liu Yang, Wang Zhao, Kuang Hongbo, Bu Jiangtao, Zhao Fuyu. Development of a Dynamic Simulation Program of AP1000 Reactor Core[J]. Nuclear Power Engineering, 2014, 35(3): 173-176. doi: 10.13832/j.jnpe.2014.03.0173
[16]	Hu Yuechun, Li Haitao, DenG Caiyu, Xu Taozhong, MO Zhengyu. Research on Method for Estimating Rapidly Water Temperature of Spent Fuels Storage Pool[J]. Nuclear Power Engineering, 2014, 35(3): 102-104. doi: 10.13832/j.jnpe.2014.03.0102
[17]	TAN Yi, WEI Shuping, DENG Lilin, LIU Xiaoli. Characteristics Study for Decay Heat and Fission Product Inventory of Reactor Core with MOX Fuel[J]. Nuclear Power Engineering, 2014, 35(2): 8-12.
[18]	Wang Chuang, XioNG Dongqing, Xu Guangzhen, Li Juan. Analysis of Spent Fuel Pool Cooling Problems of CPR1000 NPP[J]. Nuclear Power Engineering, 2014, 35(4): 90-93. doi: 10.13832/j.jnpe.2014.04.0090
[19]	WANG Yaodong, GONG Aicheng, XU Jie, ZENG Jianli. Modifications for Improving Safety Feature of Spent Fuel Pool in CPR1000 Nuclear Power Units[J]. Nuclear Power Engineering, 2013, 34(S2): 77-80.
[20]	HUANG Hongwen, LIU Hangang, MI Xiangmiao, QIAN Dazhi, YANG Xiaobin, HUANG Wen, ZHANG Zhihua. Research on Decay Heat Calculation and Measurement for Pool-Type Research Reactor[J]. Nuclear Power Engineering, 2012, 33(5): 12-15,21.