Experimental investigation on condensation heat transfer for bundle tube heat exchanger of the PCCS (Passive Containment Cooling System)

Bae, Byoung-Uhn; Kim, Seok; Park, Yu-Sun; Kang, Kyoung-Ho

doi:10.1016/j.anucene.2019.107285

Cited by 26 publications

(4 citation statements)

References 8 publications

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“…In a study conducted by Bae et al [121] at the CLASSIC facility, an experiment was carried out to scrutinize condensation heat transfer in a genuine PCCS prototype. The experiment revealed that the local HTC of the inner tubes was lower than the average value, primarily due to a shadow effect resulting from the presence of a high mass fraction of NCGs.…”

Section: Separate Effect Experimentsmentioning

confidence: 99%

Steam Condensation Heat Transfer in the Presence of Noncondensable Gases (NCGs) in Nuclear Power Plants (NPPs): A Comprehensive Review of Fundamentals, Current Status, and Prospects for Future Research

Albdour,

Addad,

Alyammahi

et al. 2024

International Journal of Energy Research

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Efficient steam condensation is crucial for safe nuclear power plant (NPP) operations, preventing pressure buildup, overheating, and the release of radioactive materials. However, the presence of noncondensable gases (NCGs), such as air, nitrogen, hydrogen, or helium, can hinder the condensation process by creating a thermal resistance layer that impedes steam diffusion and condensation on the system’s surface. Maximizing the efficiency of steam condensation requires a thorough grasp of the fundamental processes, theories, advancements, and technical hurdles. Therefore, this work thoroughly addresses these needs, with a particular emphasis on addressing the challenges posed by NCGs by dividing the work into four thematic areas. The first theme relates to a comprehensive examination of pure steam condensation phenomena, which includes an exploration of familiar condensation scenarios and various film condensation types. The second theme examines condensation in the presence of NCGs, their mixture properties, and related theories and modelling of heat and mass transfer. The third theme investigates condensation in NPP by exploring passive cooling systems and condensation phenomena under both natural and forced convection conditions during nuclear accidents, the origin of NCGs in NPP and their transportation aspects. This is followed by experimental work related to condensation scenarios and scale. Finally, the last theme looks upon the recent advancements in computational fluid dynamics (CFD) modelling of wall condensation, system analysis codes coupling with CFD, and the implementation of machine learning (ML) for predicting the condensation HTC. By bridging the gap between fundamental knowledge and practical applications, the four thematic areas presented in this work are aimed at providing a comprehensive foundation for researchers and experts in the field of steam condensation when NCGs are involved. The ultimate objective is to bolster the safety and efficacy of NPP operations by understanding the heat and mass transfer mechanisms while mitigating the risk of catastrophic events.

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Section: Separate Effect Experimentsmentioning

confidence: 99%

Steam Condensation Heat Transfer in the Presence of Noncondensable Gases (NCGs) in Nuclear Power Plants (NPPs): A Comprehensive Review of Fundamentals, Current Status, and Prospects for Future Research

Albdour,

Addad,

Alyammahi

et al. 2024

International Journal of Energy Research

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“…The gas-mixture pressure range is determined according to the engineering practice, the general maximum permissible value for containment is 0.5 MPa. The air mass frac-tion range is determined based on literature data [22]. The cooling water temperature is set at typical room temperature.…”

Section: Experimental Procedures and Conditionsmentioning

confidence: 99%

Time-Average Heat Transfer Coefficient for Steam-Air Condensation during the Dropping of Containment Pressure

Li¹,

Hui

Ke³

et al. 2022

Energies

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The passive containment cooling system (PCCS) has been applied in the new generation nuclear power plant. Previous studies mainly focused on steady-state heat transfer, but the actual heat transfer of PCCS is the transient process. Thus, investigating the transient heat transfer during the containment pressure dropping is necessary. The present study proposes a time-average condensation heat transfer coefficient (time-average condensation HTC) to characterize the intensity of transient condensation heat transfer. The time-average condensation HTC is defined as the heat absorbed per unit heat transfer area and per unit wall subcooling in a unit time. Experiments were performed to research the effect of initial gas-mixture pressure and air mass fraction on transient HTC. The result showed that the more significant gas-mixture pressure and lower air mass fraction could promote the transient-state heat transfer, especially the low air mass fraction. Based on the experimental result, a detailed empirical correlation for the time-average heat transfer coefficient is developed with an error of ±20%. Another simplified empirical correlation that only includes air mass fraction is also proposed to predict the transient heat transfer roughly. Besides, research on self-sustaining stability is also conducted to evaluate the stable operation characteristic of PCCS. The system can respond quickly and then run to a new steady state after interference during the long-term operation of PCCS. The phenomenon above implies that PCCS has good self-sustaining stability.

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“…They built and simulated a model for a single tube as a prototype to test the condensation of HT of HEX. The results indicated that the tube degradation takes place with time due to thermal effect, since the non-condensable gas concentration increased due to an accumulation around the inside tubes [14].Cai et. al concentrated on improving the tube metal properties of the steam generator in NPP.…”

Section: -Introductionmentioning

confidence: 99%

“…Ayodeji and Liu studied flow and HT of supercritical water in supercritical boiler water and they investigated the wall tube with numerical simulation and they found that, the HT coefficient increases by increasing the inlet flow rate [14].Bae et. al concentrated-on validation of HT condensation in nuclear reactor passive cooling system.…”

Section: -Introductionmentioning

confidence: 99%

Efficient Evaluation of Heat Exchangers Behaviour in Nuclear Power Plants

Emarah

Kasban

2021

Arab Journal of Nuclear Sciences and Applications

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This paper studies the performance of the primary and secondary flow paths of the heat exchangers (HEXs) in the Nuclear Power Plants (NPPs). Explicit solutions for the wall temperature, primary and secondary wall temperatures of the HEX are presented. Therefore, closed form expressions for wall temperature, primary and secondary wall temperature are proposed. Moreover, performance analysis of HEX is investigated. The various effects of pipe wall heat capacities, perimeter, fluid heat transfer (HT) coefficient and wall HT coefficient on the HEX are evaluated. The obtained results confirm that the surface contact between the two fluid passes reduces the temperature to some extent at 5 seconds. As a final point of observation, the temperature distributions through the HEX structure increases with the decrease of its perimeter. The proposed work allows more control of the HT process within the HEX. Consequently, the performance of NPPs can be improved.

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Experimental investigation on condensation heat transfer for bundle tube heat exchanger of the PCCS (Passive Containment Cooling System)

Cited by 26 publications

References 8 publications

Steam Condensation Heat Transfer in the Presence of Noncondensable Gases (NCGs) in Nuclear Power Plants (NPPs): A Comprehensive Review of Fundamentals, Current Status, and Prospects for Future Research

Steam Condensation Heat Transfer in the Presence of Noncondensable Gases (NCGs) in Nuclear Power Plants (NPPs): A Comprehensive Review of Fundamentals, Current Status, and Prospects for Future Research

Time-Average Heat Transfer Coefficient for Steam-Air Condensation during the Dropping of Containment Pressure

Efficient Evaluation of Heat Exchangers Behaviour in Nuclear Power Plants

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