Experimental and numerical investigation of local bubble parameters for subcooled flow boiling in a pressurized annulus
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作者:
Alatrash, Yazan
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Univ Sci & Technol, Adv Nucl Syst Engn Dept, 217 Gajeong Ro, Daejeon, South Korea
Korea Atom Energy Res Inst, Daedeok Daero 989-111, Daejeon 34057, South KoreaUniv Sci & Technol, Adv Nucl Syst Engn Dept, 217 Gajeong Ro, Daejeon, South Korea
Alatrash, Yazan
[1
,2
]
Cho, Yun-Je
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Korea Atom Energy Res Inst, Daedeok Daero 989-111, Daejeon 34057, South KoreaUniv Sci & Technol, Adv Nucl Syst Engn Dept, 217 Gajeong Ro, Daejeon, South Korea
Cho, Yun-Je
[2
]
Yoon, Han -Young
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Univ Sci & Technol, Adv Nucl Syst Engn Dept, 217 Gajeong Ro, Daejeon, South Korea
Korea Atom Energy Res Inst, Daedeok Daero 989-111, Daejeon 34057, South KoreaUniv Sci & Technol, Adv Nucl Syst Engn Dept, 217 Gajeong Ro, Daejeon, South Korea
Yoon, Han -Young
[1
,2
]
Song, Chul-Hwa
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Univ Sci & Technol, Adv Nucl Syst Engn Dept, 217 Gajeong Ro, Daejeon, South Korea
Korea Atom Energy Res Inst, Daedeok Daero 989-111, Daejeon 34057, South KoreaUniv Sci & Technol, Adv Nucl Syst Engn Dept, 217 Gajeong Ro, Daejeon, South Korea
Song, Chul-Hwa
[1
,2
]
Chu, In-Cheol
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Korea Atom Energy Res Inst, Daedeok Daero 989-111, Daejeon 34057, South KoreaUniv Sci & Technol, Adv Nucl Syst Engn Dept, 217 Gajeong Ro, Daejeon, South Korea
Chu, In-Cheol
[2
]
机构:
[1] Univ Sci & Technol, Adv Nucl Syst Engn Dept, 217 Gajeong Ro, Daejeon, South Korea
[2] Korea Atom Energy Res Inst, Daedeok Daero 989-111, Daejeon 34057, South Korea
The wall boiling models adopted in the Computational Multi-Fluid Dynamics (CMFD) tools rely on empir-ical correlations for closures, which causes considerable uncertainties in their results. Thus, well-defined experimental data for local boiling parameters are essential for the development and validation of the wall boiling constitutive models. This paper presents new experimental data on the local bubble parame-ters and the wall temperatures along the heated tube for the subcooled flow boiling under high-pressure conditions. The radial distributions of the bubble parameters, namely, void fraction, bubble velocity, in-terfacial area concentration, and Sauter mean diameter were measured at multiple elevations to evaluate their development along the flow. Furthermore, the experimental data set was utilized to validate physi-cal models for predicting subcooled flow boiling using a CMFD code. The source of discrepancies between the experimental and calculated results were analyzed and possible directions for research in subcooled flow boiling under high-pressure conditions were defined.(c) 2022 Published by Elsevier Ltd.
机构:
Jeju Natl Univ, Inst Nucl Sci & Technol, 102 Jejudaehak Ro, Jeju Si 63243, Jeju, South KoreaJeju Natl Univ, Dept Nucl & Energy Engn, 102 Jejudaehak Ro, Jeju Si 63243, Jeju, South Korea
Park, Il Woong
Yoo, Ji-Woong
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Jeju Natl Univ, Dept Nucl & Energy Engn, 102 Jejudaehak Ro, Jeju Si 63243, Jeju, South KoreaJeju Natl Univ, Dept Nucl & Energy Engn, 102 Jejudaehak Ro, Jeju Si 63243, Jeju, South Korea
Yoo, Ji-Woong
Kim, Sin
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机构:
Chung Ang Univ, Sch Energy Syst Engn, 84 Heukseok Ro, Seoul 06974, South KoreaJeju Natl Univ, Dept Nucl & Energy Engn, 102 Jejudaehak Ro, Jeju Si 63243, Jeju, South Korea
机构:
Indian Inst Technol, Dept Mech Engn, Madras 600036, Tamil Nadu, IndiaGovt Andhra Pradesh, Dept Tech Educ, Fac Mech Engn, Hyderabad 500063, Andhra Pradesh, India