Study on Coolant Flow Characteristics for Residual Air Criteria Improvement of Primary Loop Dynamic Venting

Zhang Zhao; Sheng Guolong; Sun Kaibao; Zhao Fuyu; Chong Daotong; Yan Junjie

Volume 40 Issue 5

Oct. 2019

Turn off MathJax

Article Contents

Abstract

References

Article Navigation > Nuclear Power Engineering > 2019 > 40(5): 35-40

Zhang Zhao, Sheng Guolong, Sun Kaibao, Zhao Fuyu, Chong Daotong, Yan Junjie. Study on Coolant Flow Characteristics for Residual Air Criteria Improvement of Primary Loop Dynamic Venting[J]. Nuclear Power Engineering, 2019, 40(5): 35-40.

Citation:

PDF( 0 KB)

Study on Coolant Flow Characteristics for Residual Air Criteria Improvement of Primary Loop Dynamic Venting

Publish Date: 2019-10-15

Abstract

Abstract

According to the improvement proposal for the residual air criteria of the primary loop dynamic venting, the pressure prediction method for the main primary nodes and the judgment method for the two-phase coolant flow are investigated. The thermo-hydraulics model for the primary loop and its auxiliary systems are proposed. When the residual air criteria is raised to 24 normal cubic meters, the startup transient process of reactor coolant pumps are simulated with the models, to obtain the pressure of the main nodes in the primary loop. Based on the gas resolution and released model, the change trend of nitrogen saturation solubility and oxygen saturation solubility are obtained. The results indicate that the pressures of the main nodes are within the normal operation limit; the nitrogen and oxygen cannot release from the coolant and cannot form a two-phase flow. Therefore, in terms of the coolant flow characteristics, the improvement for the residual air criteria to 24 normal cubic meters is feasible.
- Primary loop dynamic venting,
- Residual air criteria,
- Coolant,
- Flow characteristics

FullText(HTML)

References(0)

References

Relative Articles

[1]	Du Lipeng, Song Shangdian, Cai Weihua, Jiang Zeping, Cheng Qi, Zhang Wenchao, Jin Guangyuan. Numerical Study on Characteristics of Subcooled Flow Boiling with the Coupling Effect of 3×3 Petal-Shaped Fuel Rods and Coolant[J]. Nuclear Power Engineering, 2024, 45(4): 87-95. doi: 10.13832/j.jnpe.2024.04.0087
[2]	Luan Xingjian, Wang Wen, Song Jiahao, Han Fei, Jiang Erhui, Cheng Kun, Yang Fan. Analysis on Flow Distribution Characteristics of Steam Generator under Natural Circulation Condition[J]. Nuclear Power Engineering, 2024, 45(4): 103-110. doi: 10.13832/j.jnpe.2024.04.0103
[3]	Xiong Jun, Lyu Weifeng, Guo Runchun, Gao Yaoyi, Jiang Zhenyu. Research on Evaluation Method of Actinide Nuclide Activities in Primary Coolant System of Pressurized Water Reactor Nuclear Power Plant[J]. Nuclear Power Engineering, 2024, 45(2): 47-52. doi: 10.13832/j.jnpe.2024.02.0047
[4]	Guo Zifang, Yang Yu, Lin Mingzhang, Cao Qi, Tang Jia, Lin Yunliang, Lin Zijian. Study on the Steady γ-Radiolysis of Ammonia Solution[J]. Nuclear Power Engineering, 2023, 44(3): 217-222. doi: 10.13832/j.jnpe.2023.03.0217
[5]	Fei Junjie, Liu Minyun, Xi Dapeng, Tang Jia, Liu Ruilong, Zan Yuanfeng, Huang Yanping. Numerical Investigation of the Influence of Microchannel Diffusion Welded Heat Exchanger Head Structure on Flow Characteristics[J]. Nuclear Power Engineering, 2023, 44(S2): 176-183. doi: 10.13832/j.jnpe.2023.S2.0176
[6]	Li Fuhai, Lin Yunliang, Lin Zijian, Lin Genxian, Guo Zifang, Fang Jun, Lin Mingzhang. Research on Calculation of Coolant Radiolysis Products in Operating Conditions during the Shutdown of PWRs[J]. Nuclear Power Engineering, 2023, 44(3): 202-209. doi: 10.13832/j.jnpe.2023.03.0202
[7]	Xu Yu, HuangFu Zeyu, Xu Jianqun, Tian Peiyu, Li Chunmei, Cheng Xiang, Yan Siwei, Liao Xianwei. Research on Modeling and Simulation of Once-Through Steam Generator[J]. Nuclear Power Engineering, 2021, 42(1): 154-160. doi: 10.13832/j.jnpe.2021.01.0154
[8]	Liu Mengyao, Kang Can, Ding Kejin, Li Bing. Instantaneous Flow and Structural Characteristics During Opening of a Nuclear Check Valve[J]. Nuclear Power Engineering, 2020, 41(3): 45-51. doi: 10.13832/j.jnpe.2020.03.0045
[9]	Zhang Yingqiang. Research and Application of Vacuum Exhaust Method in Primary Loop of Ling’ao Nuclear Power Plant[J]. Nuclear Power Engineering, 2018, 39(5): 91-94. doi: 10.13832/j.jnpe.2018.05.0091
[10]	Wang Qing, Fang Yonggang, Chu Qibao, Lu Yan, Xu Yu, Li Hailong, Wen Jing. Effect of Damping Parameters on Seismic Analysis of Nuclear Reactor Coolant Loop[J]. Nuclear Power Engineering, 2017, 38(4): 27-30. doi: 10.13832/j.jnpe.2017.04.0027
[11]	Wang Cong, Lu Daogang, Yao Zhipeng, Cao Qiong, Awais Ahmad, Zhang Shuming. PIV Experiment Research on Flow Pattern in Secondary Side of Steam Generator Based on a Visible Experimental Facility[J]. Nuclear Power Engineering, 2017, 38(5): 4-9. doi: 10.13832/j.jnpe.2017.05.0004
[12]	Zheng Jie, Chen Zhao, Zhao Pengcheng, Chen Hongli. Study on Flow Similarity Laws between Water and Liquid Lead-Bismuth under Natural Circulation[J]. Nuclear Power Engineering, 2016, 37(3): 31-33. doi: 10.13832/j.jnpe.2016.03.0031
[13]	Liu Jinhua, Wen Juhua, Gong Bin, Xia Xiaojiao, Jiang E, Zhao Yongfu, Zhou Zhiru. Study on Application of Enriched Boric in Primary Coolant of Nuclear Power Plants[J]. Nuclear Power Engineering, 2015, 36(3): 110-113. doi: 10.13832/j.jnpe.2015.03.0110
[14]	Yao Yangui, Shi Yang, Zhang Kai, Lu Mingchao. Analysis of Relevant Problems of Shape Flow Resistance in Nuclear Power Plants[J]. Nuclear Power Engineering, 2015, 36(5): 83-86. doi: 10.13832/j.jnpe.2015.05.0083
[15]	CHEN Chao, WANG Zhengguang, XIE Enfei. Study on Primary Coolant pH Regimes of Nuclear Power Plants[J]. Nuclear Power Engineering, 2013, 34(S2): 47-50.
[16]	WANG Xiu-li, YUAN Shou-qi, ZHU Rong-sheng, YU Zhi-jun. Transient Flow Characteristics of Nuclear Reactor Coolant Pump in Recessive Cavitation Transition Process[J]. Nuclear Power Engineering, 2013, 34(3): 71-76.
[17]	HU Jian-jun, TANG Bin, YANG Bin. Research on Calculation of PWR Coolant ¹⁶N and ¹⁷N Activity Source Terms Based on Transport Calculation Method[J]. Nuclear Power Engineering, 2013, 34(5): 16-19.
[18]	GONG Hou-jun, YANG Xing-tuan, HUANG Yan-ping, JIANG Sheng-yao. Study on Flow Characteristics of Integral Reactor Test Facility under Rolling Motion without Heating[J]. Nuclear Power Engineering, 2013, 34(3): 77-81.
[19]	QIAN Libo, TIAN Wenxi, QIU Suizheng, SU Guanghui, LI Yong, HUANG Yanping, YAN Xiao. Research on Model of Additional Forces of Ocean Conditions in One-Dimensional Coolant Channel[J]. Nuclear Power Engineering, 2012, 33(2): 104-109.
[20]	LU Chuan, ZHANG Yong, LU Jian-chao, DONG Hua-ping. Analysis of Flow Behavior of Coolant in Natural Circulation Reactor Based on Computational Fluid Dynamics[J]. Nuclear Power Engineering, 2012, 33(S1): 111-114,118.