Fouling rate of calcium sulphate is investigated based on the development of a multicomponent model to handle the two-phase flow of liquid mixture and vapour bubbles for the sub-cooled flow boiling. Effects of operating conditions, as well as wall roughness, on the heat transfer and fouling rate are studied. Fouling resistance increased with increasing fluid velocity. Deposition rate increases rapidly with increasing surface temperature while heat transfer coefficient decreases at higher surface temperature. Nevertheless, the bulk temperature does not strongly influence the heat transfer coefficient, thermal resistance and fouling rate. (C) 2015 Elsevier Ltd. All rights reserved.
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Harbin Engn Univ, Heilongjiang Prov Key Lab Nucl Power Syst & Equip, Harbin 150001, Peoples R ChinaHarbin Engn Univ, Heilongjiang Prov Key Lab Nucl Power Syst & Equip, Harbin 150001, Peoples R China
Liao, Hengji
Yan, Xiao
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Harbin Engn Univ, Heilongjiang Prov Key Lab Nucl Power Syst & Equip, Harbin 150001, Peoples R ChinaHarbin Engn Univ, Heilongjiang Prov Key Lab Nucl Power Syst & Equip, Harbin 150001, Peoples R China
Yan, Xiao
Gu, Haifeng
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Harbin Engn Univ, Heilongjiang Prov Key Lab Nucl Power Syst & Equip, Harbin 150001, Peoples R ChinaHarbin Engn Univ, Heilongjiang Prov Key Lab Nucl Power Syst & Equip, Harbin 150001, Peoples R China
Gu, Haifeng
Qin, Shengjie
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Nucl Power Inst China, Reactor Engn Res Subinst, Chengdu 610213, Peoples R ChinaHarbin Engn Univ, Heilongjiang Prov Key Lab Nucl Power Syst & Equip, Harbin 150001, Peoples R China
Qin, Shengjie
PROCEEDINGS OF 2024 31ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 7, ICONE31 2024,
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Heilongjiang Provincial Key Laboratory of Nuclear Power System & Equipment, College of Nuclear Science and Technology, Harbin Engineering University, Harbin,150001, ChinaHeilongjiang Provincial Key Laboratory of Nuclear Power System & Equipment, College of Nuclear Science and Technology, Harbin Engineering University, Harbin,150001, China
Li, Zongkun
Cheng, Jie
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Heilongjiang Provincial Key Laboratory of Nuclear Power System & Equipment, College of Nuclear Science and Technology, Harbin Engineering University, Harbin,150001, ChinaHeilongjiang Provincial Key Laboratory of Nuclear Power System & Equipment, College of Nuclear Science and Technology, Harbin Engineering University, Harbin,150001, China
Cheng, Jie
Zhou, Xuwei
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Heilongjiang Provincial Key Laboratory of Nuclear Power System & Equipment, College of Nuclear Science and Technology, Harbin Engineering University, Harbin,150001, ChinaHeilongjiang Provincial Key Laboratory of Nuclear Power System & Equipment, College of Nuclear Science and Technology, Harbin Engineering University, Harbin,150001, China
Zhou, Xuwei
Zeng, Xiaobo
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Heilongjiang Provincial Key Laboratory of Nuclear Power System & Equipment, College of Nuclear Science and Technology, Harbin Engineering University, Harbin,150001, ChinaHeilongjiang Provincial Key Laboratory of Nuclear Power System & Equipment, College of Nuclear Science and Technology, Harbin Engineering University, Harbin,150001, China
Zeng, Xiaobo
Cao, Xiaxin
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Heilongjiang Provincial Key Laboratory of Nuclear Power System & Equipment, College of Nuclear Science and Technology, Harbin Engineering University, Harbin,150001, ChinaHeilongjiang Provincial Key Laboratory of Nuclear Power System & Equipment, College of Nuclear Science and Technology, Harbin Engineering University, Harbin,150001, China
Cao, Xiaxin
Fan, Guangming
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Heilongjiang Provincial Key Laboratory of Nuclear Power System & Equipment, College of Nuclear Science and Technology, Harbin Engineering University, Harbin,150001, ChinaHeilongjiang Provincial Key Laboratory of Nuclear Power System & Equipment, College of Nuclear Science and Technology, Harbin Engineering University, Harbin,150001, China