Development and assessment of a new CHF mechanistic model for subcooled and low quality flow boiling
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作者:
Liu, Wei
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Nucl Power Inst China, State Key Lab Reactor Syst Design Technol, Chengdu 610213, Peoples R ChinaNucl Power Inst China, State Key Lab Reactor Syst Design Technol, Chengdu 610213, Peoples R China
Liu, Wei
[1
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Peng, Shinian
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Nucl Power Inst China, State Key Lab Reactor Syst Design Technol, Chengdu 610213, Peoples R ChinaNucl Power Inst China, State Key Lab Reactor Syst Design Technol, Chengdu 610213, Peoples R China
Peng, Shinian
[1
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Jiang, Guangming
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Nucl Power Inst China, State Key Lab Reactor Syst Design Technol, Chengdu 610213, Peoples R ChinaNucl Power Inst China, State Key Lab Reactor Syst Design Technol, Chengdu 610213, Peoples R China
Jiang, Guangming
[1
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Liu, Yu
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Nucl Power Inst China, State Key Lab Reactor Syst Design Technol, Chengdu 610213, Peoples R ChinaNucl Power Inst China, State Key Lab Reactor Syst Design Technol, Chengdu 610213, Peoples R China
Liu, Yu
[1
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机构:
[1] Nucl Power Inst China, State Key Lab Reactor Syst Design Technol, Chengdu 610213, Peoples R China
Under subcooled and low quality flow boiling conditions, a general critical heat flux (CHF) mechanistic model is essential to the thermal-hydraulic design and safety analysis, especially at the conceptual design stage of a new pressurized water reactor (PWR). In this study, an overview of the physical mechanisms behind the most common CHF models was carried out and the additional effects to be considered in a new CHF model were indicated. Then, based on the mechanism of superheated liquid layer depletion, the net mass transfer from the bulk liquid to the superheated liquid layer caused by turbulent velocity fluctuations of flowing bubbles was determined and a new calculation method of superheated liquid layer thickness was developed. After matching with other constitutive equations, a novel CHF mechanistic model for subcooled and low quality flow boiling conditions has been developed. Furthermore, the present CHF mechanistic model was validated with 5 x 5 rod bundle CHF experimental data of Nuclear Power Institute of China (NPIC) and compared with other CHF models and CF-DRW correlation. Finally, the distribution of M/P was evaluated and the advantage of the present CHF mechanistic model was discussed. The results show that the present CHF model performs as well as the CF-DRW correlation and is superior to other well established CHF models without any correction factors or empirical constants from experimental data. (C) 2020 Elsevier Ltd. All rights reserved.
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Korea Adv Inst Sci & Technol, 373-1 Guseong Dong, Daejeon 305701, South KoreaKorea Adv Inst Sci & Technol, 373-1 Guseong Dong, Daejeon 305701, South Korea
Song, Jung Hyun
Jung, Jun Yeong
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Korea Adv Inst Sci & Technol, 373-1 Guseong Dong, Daejeon 305701, South KoreaKorea Adv Inst Sci & Technol, 373-1 Guseong Dong, Daejeon 305701, South Korea
Jung, Jun Yeong
Ch, Soon Heung
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Handong Univ, Handong Ro 558, Pohang 791708, South KoreaKorea Adv Inst Sci & Technol, 373-1 Guseong Dong, Daejeon 305701, South Korea
Ch, Soon Heung
Jeong, Yong Hoon
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Korea Adv Inst Sci & Technol, 373-1 Guseong Dong, Daejeon 305701, South KoreaKorea Adv Inst Sci & Technol, 373-1 Guseong Dong, Daejeon 305701, South Korea
机构:
Xi An Jiao Tong Univ, Sch Chem Engn & Technol, Xian 710049, Shaanxi, Peoples R ChinaXi An Jiao Tong Univ, Sch Chem Engn & Technol, Xian 710049, Shaanxi, Peoples R China
Yuan, Bo
Zhang, Yonghai
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Xi An Jiao Tong Univ, Sch Chem Engn & Technol, Xian 710049, Shaanxi, Peoples R ChinaXi An Jiao Tong Univ, Sch Chem Engn & Technol, Xian 710049, Shaanxi, Peoples R China
Zhang, Yonghai
Wei, Jinjia
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Xi An Jiao Tong Univ, Sch Chem Engn & Technol, Xian 710049, Shaanxi, Peoples R China
Xi An Jiao Tong Univ, State Key Lab Multiphase Flow Power Engn, Xian 710049, Shaanxi, Peoples R ChinaXi An Jiao Tong Univ, Sch Chem Engn & Technol, Xian 710049, Shaanxi, Peoples R China
机构:
Idaho Natl Lab, 2525 North Fremont Ave,POB 3860, Idaho Falls, ID 83415 USAIdaho Natl Lab, 2525 North Fremont Ave,POB 3860, Idaho Falls, ID 83415 USA
Yoo, Junsoo
Estrada-Perez, Carlos E.
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Texas A&M Univ, Dept Nucl Engn, College Stn, TX 77843 USAIdaho Natl Lab, 2525 North Fremont Ave,POB 3860, Idaho Falls, ID 83415 USA
Estrada-Perez, Carlos E.
Hassan, Yassin A.
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Texas A&M Univ, Dept Nucl Engn, College Stn, TX 77843 USAIdaho Natl Lab, 2525 North Fremont Ave,POB 3860, Idaho Falls, ID 83415 USA