General Assessment of Convection Heat Transfer Correlations for Multiple Geometries and Fluids at Supercritical Pressure

Zahlan, H.; Leung, Laurence; Huang, Yanping; Liu, Guangxu

doi:10.12943/cnr.2017.00003

Cited by 3 publications

(10 citation statements)

References 22 publications

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“…In contrast to that study, the present work separated the HTD data from the entire tube database, and assessed all tube correlations against normal and deteriorated heat transfer (DHT) databases separately. The study by Zahlan et al [4] also revealed that some of the applied CO 2 correlations approximated experimental water data closer than most of the investigated water data-based correlations and vice versa. In addition, some correlations, originally developed for NHT, approximated well the entire database.…”

Section: Introductionmentioning

confidence: 84%

“…In addition to water and CO 2 , the databank comprises measurements collected with refrigerants and helium for round tubes, annuli, and rod bundle subassemblies. Zahlan et al [4] reported a description of the CNL databank compiled prior to 2016 and showed ranges of flow conditions of the databases.…”

Section: Cnl Databank Of Scht and Assessed Correlationsmentioning

confidence: 99%

“…The databases were subjected to screening and quality assurance tests, as discussed in Zahlan et al [4], where duplicates, outliers, and data not complying with heat balance were removed.…”

Section: Tube Databases For Water and Comentioning

confidence: 99%

“…Zahlan et al [4] discussed and tabulated more than 20 round-tube correlations for single phase and SCHT. They also reported a compilation of available SCHT correlations for rod bundle geometries.…”

Section: Assessed Tube Data-based Correlationsmentioning

confidence: 99%

“…Recently, Zahlan et al [4] assessed available correlations against entire databases from the CNL databank. In contrast to that study, the present work separated the HTD data from the entire tube database, and assessed all tube correlations against normal and deteriorated heat transfer (DHT) databases separately.…”

Section: Introductionmentioning

confidence: 99%

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An Assessment of Round Tube Correlations for Convective Heat Transfer at Supercritical Pressure

Zahlan

Leung

2017

CNL Nuclear Review

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Section: Introductionmentioning

confidence: 84%

Section: Cnl Databank Of Scht and Assessed Correlationsmentioning

confidence: 99%

“…The databases were subjected to screening and quality assurance tests, as discussed in Zahlan et al [4], where duplicates, outliers, and data not complying with heat balance were removed.…”

Section: Tube Databases For Water and Comentioning

confidence: 99%

Section: Assessed Tube Data-based Correlationsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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An Assessment of Round Tube Correlations for Convective Heat Transfer at Supercritical Pressure

Zahlan

Leung

2017

CNL Nuclear Review

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Assessment of heat transfer correlations in the sub-channels of proposed rod bundle geometry for supercritical water reactor

Debrah

Shitsi

Chabi

et al. 2019

Heliyon

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There are heat transfer correlations for heat transfer analysis in single tube geometries after several experimental and theoretical heat transfer studies in these single tube geometries. This is not the case for heat transfer analysis in rod bundle geometry with regard to proposed square fuel assembly of the Supercritical-Water-Cooled Reactor (SCWR) European Atomic Energy (EURATOM) design. Thus limited heat transfer studies exist on rod bundle geometry at supercritical pressures. Heat transfer correlations with accurate prediction capabilities of coolant and wall temperatures will be helpful in carrying out heat transfer studies at supercritical pressures. This paper presents the performance of twelve selected heat transfer correlations assessed on the 1/8th bare square fuel assembly of the SCWR EURATOM design using Simulation of Turbulent flow in Arbitrary Regions Computational Continuum Mechanics C ++ based code (STAR-CCM + CFD code). The obtained numerical results were compared with the results obtained by Waata numerical experimentation. Overall, the Cheng et al. correlation provided the most satisfying prediction for the wall temperatures in all the sub-channels and captured closely Wataa's Numerical data. The maximum wall temperature was obtained in sub-channel 9, the hottest sub-channel and exceeded the design limit 620 °C by 60 °C for the Cheng correlation. The difference in temperature between the hottest and coldest sub-channels 9 and 1 respectively was approximately 80 °C. It was found that Cheng correlation is best suited for heat transfer prediction in rod bundle geometry at supercritical pressures with regard to the proposed square fuel assembly of the SCWR EURATOM design. It was also found that the different numerical tools adopted for this study and Waata study were able to capture the trends of normal, enhanced and deteriorated heat transfer regimes normally observed at supercritical pressures. Nevertheless, experimental investigations involving rod bundles adopted in this study should be conducted to validate the results obtained numerically and address the inconsistency of the conclusions drawn when compared with Waata data and other similar studies.

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Assessment of Convective Heat Transfer Correlations Against an Expanded Database for Different Fluids at Supercritical Pressures

Zahlan

Leung

Liu

2017

Journal of Nuclear Engineering and Radiation Science

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Canadian Nuclear Laboratories (CNL) has recently expanded the supercritical heat transfer (SCHT) databank with additional data provided by the Nuclear Power Institute of China (NPIC). These additional data cover flow conditions beyond the current databank, and are applicable for improving or validating existing correlations. The expanded databank comprises more than 41,000 points of heat-transfer measurements with different fluids flowing vertically upward in tubes, annuli, and bundles at supercritical (SC) pressures. It has been applied in assessing the prediction accuracy of 24 heat-transfer correlations, which were derived from experimental data obtained with water or nonaqueous fluids (such as carbon dioxide) flowing in tubes. For the correlation assessment, a sensitivity analysis has been performed by applying the measured wall temperature as an independent parameter. The assessment against the bundle data was based on cross-sectional-averaged flow conditions and the hydraulic diameter. The iterative approach (i.e., without prior knowledge of the wall temperature) overpredicted the wall temperature, which is conservative in safety analyses.

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General Assessment of Convection Heat Transfer Correlations for Multiple Geometries and Fluids at Supercritical Pressure

Abstract: Nomenclature c p specific heat capacity at constant pressure (J kg

Cited by 3 publications

References 22 publications

An Assessment of Round Tube Correlations for Convective Heat Transfer at Supercritical Pressure

An Assessment of Round Tube Correlations for Convective Heat Transfer at Supercritical Pressure

Assessment of heat transfer correlations in the sub-channels of proposed rod bundle geometry for supercritical water reactor

Assessment of Convective Heat Transfer Correlations Against an Expanded Database for Different Fluids at Supercritical Pressures

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