Development of the analysis tool for the water cooling type passive residual heat removal system of Chinese pressurized reactor
被引:11
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作者:
Huang, Tao
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机构:
Xi An Jiao Tong Univ, Dept Nucl Sci & Technol, Xian 710049, Peoples R ChinaXi An Jiao Tong Univ, Dept Nucl Sci & Technol, Xian 710049, Peoples R China
Huang, Tao
[1
]
Zhang, Y. P.
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机构:
Xi An Jiao Tong Univ, Dept Nucl Sci & Technol, Xian 710049, Peoples R ChinaXi An Jiao Tong Univ, Dept Nucl Sci & Technol, Xian 710049, Peoples R China
Zhang, Y. P.
[1
]
Gong, Houjun
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机构:
Nucl Power Inst China, CNNC Key Lab Nucl Reactor Thermal Hydraul Technol, Chengdu 610041, Peoples R ChinaXi An Jiao Tong Univ, Dept Nucl Sci & Technol, Xian 710049, Peoples R China
Gong, Houjun
[2
]
Tian, W. X.
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机构:
Xi An Jiao Tong Univ, Dept Nucl Sci & Technol, Xian 710049, Peoples R ChinaXi An Jiao Tong Univ, Dept Nucl Sci & Technol, Xian 710049, Peoples R China
Tian, W. X.
[1
]
Su, G. H.
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机构:
Xi An Jiao Tong Univ, Dept Nucl Sci & Technol, Xian 710049, Peoples R ChinaXi An Jiao Tong Univ, Dept Nucl Sci & Technol, Xian 710049, Peoples R China
Su, G. H.
[1
]
Qiu, S. Z.
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机构:
Xi An Jiao Tong Univ, Dept Nucl Sci & Technol, Xian 710049, Peoples R ChinaXi An Jiao Tong Univ, Dept Nucl Sci & Technol, Xian 710049, Peoples R China
Qiu, S. Z.
[1
]
机构:
[1] Xi An Jiao Tong Univ, Dept Nucl Sci & Technol, Xian 710049, Peoples R China
[2] Nucl Power Inst China, CNNC Key Lab Nucl Reactor Thermal Hydraul Technol, Chengdu 610041, Peoples R China
Analysis tool;
Water cooling;
PRHRS;
SBO accident;
TRANSIENT ANALYSES;
DESIGN;
D O I:
10.1016/j.pnucene.2016.03.019
中图分类号:
TL [原子能技术];
O571 [原子核物理学];
学科分类号:
0827 ;
082701 ;
摘要:
An innovative design for Chinese pressurized reactor is the steam generator (SG) secondary side water cooling passive residual heat removal system (PRHRS). The new design is expected to improve reliability and safety of the Chinese pressurized reactor during the event of feed line break or station blackout (SBO) accident. The new system is comprised of a SG, a cooling water pool, a heat exchanger (HX), an emergency makeup tank (EMT) and corresponding valves and pipes. In order to evaluate the reliability of the water cooling PRHRS, an analysis tool was developed based on the drift flux mixture flow model. The preliminary validation of the analysis tool was made by comparing to the experimental data of ESPRIT facility. Calculation results under both high pressure condition and low pressure condition fitted the experimental data remarkably well. A hypothetical SBO accident was studied by taking the residual power table under SBO accident as the input condition of the analysis tool. The calculation results showed that the EMT could supply the water to the SG shell side successfully during SBO accident. The residual power could be taken away successfully by the two-phase natural circulation established in the water cooling PRHRS loop. Results indicate the analysis tool can be used to study the steady and transient operating characteristics of the water cooling PRHRS during some accidents of the Chinese pressurized reactor. The present work has very important realistic significance to the engineering design and assessment of the water cooling PRHRS for Chinese NPPs. (C) 2016 Elsevier Ltd. All rights reserved.
机构:
Hanyang Univ, Dept Nucl Engn, 222 Wangsimni Ro, Seoul 04763, South KoreaHanyang Univ, Dept Nucl Engn, 222 Wangsimni Ro, Seoul 04763, South Korea
Na, Min Wook
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机构:
Shin, Doyoung
Park, Jae Hyung
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机构:
Hanyang Univ, Dept Nucl Engn, 222 Wangsimni Ro, Seoul 04763, South KoreaHanyang Univ, Dept Nucl Engn, 222 Wangsimni Ro, Seoul 04763, South Korea
Park, Jae Hyung
Lee, Jeong Ik
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机构:
Korea Adv Inst Sci & Technol, Dept Nucl & Quantum Engn, 291 Daehak Ro, Daejeon 34141, South KoreaHanyang Univ, Dept Nucl Engn, 222 Wangsimni Ro, Seoul 04763, South Korea
Lee, Jeong Ik
Kim, Sung Joong
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机构:
Hanyang Univ, Dept Nucl Engn, 222 Wangsimni Ro, Seoul 04763, South Korea
Hanyang Univ, Inst Nano Sci & Technol, 222 Wangsimni Ro, Seoul 04763, South KoreaHanyang Univ, Dept Nucl Engn, 222 Wangsimni Ro, Seoul 04763, South Korea
机构:
Xi An Jiao Tong Univ, State Key Lab Multiphase Flow Power Engn, Sch Nucl Sci & Technol, Xian 710049, Peoples R ChinaXi An Jiao Tong Univ, State Key Lab Multiphase Flow Power Engn, Sch Nucl Sci & Technol, Xian 710049, Peoples R China
Wu, Y. W.
Su, G. H.
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机构:
Xi An Jiao Tong Univ, State Key Lab Multiphase Flow Power Engn, Sch Nucl Sci & Technol, Xian 710049, Peoples R ChinaXi An Jiao Tong Univ, State Key Lab Multiphase Flow Power Engn, Sch Nucl Sci & Technol, Xian 710049, Peoples R China
Su, G. H.
Qiu, Suizheng
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机构:
Xi An Jiao Tong Univ, State Key Lab Multiphase Flow Power Engn, Sch Nucl Sci & Technol, Xian 710049, Peoples R ChinaXi An Jiao Tong Univ, State Key Lab Multiphase Flow Power Engn, Sch Nucl Sci & Technol, Xian 710049, Peoples R China
Qiu, Suizheng
Tian, Wenxi
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Xi An Jiao Tong Univ, State Key Lab Multiphase Flow Power Engn, Sch Nucl Sci & Technol, Xian 710049, Peoples R ChinaXi An Jiao Tong Univ, State Key Lab Multiphase Flow Power Engn, Sch Nucl Sci & Technol, Xian 710049, Peoples R China
机构:
Korea Atom Energy Res Inst, Thermal Hydraul Safety Res Div, Taejon 305353, South KoreaKorea Atom Energy Res Inst, Thermal Hydraul Safety Res Div, Taejon 305353, South Korea
Park, Hyun-Sik
Choi, Ki-Yong
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Korea Atom Energy Res Inst, Thermal Hydraul Safety Res Div, Taejon 305353, South KoreaKorea Atom Energy Res Inst, Thermal Hydraul Safety Res Div, Taejon 305353, South Korea
Choi, Ki-Yong
Cho, Seok
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Korea Atom Energy Res Inst, Thermal Hydraul Safety Res Div, Taejon 305353, South KoreaKorea Atom Energy Res Inst, Thermal Hydraul Safety Res Div, Taejon 305353, South Korea
Cho, Seok
Yi, Sung-Jae
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Korea Atom Energy Res Inst, Thermal Hydraul Safety Res Div, Taejon 305353, South KoreaKorea Atom Energy Res Inst, Thermal Hydraul Safety Res Div, Taejon 305353, South Korea
Yi, Sung-Jae
Park, Choon-Kyun
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Korea Atom Energy Res Inst, Thermal Hydraul Safety Res Div, Taejon 305353, South KoreaKorea Atom Energy Res Inst, Thermal Hydraul Safety Res Div, Taejon 305353, South Korea
Park, Choon-Kyun
Chung, Moon-Ki
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机构:
Korea Atom Energy Res Inst, Thermal Hydraul Safety Res Div, Taejon 305353, South KoreaKorea Atom Energy Res Inst, Thermal Hydraul Safety Res Div, Taejon 305353, South Korea