Assessment of heat transfer correlations in the sub-channels of proposed rod bundle geometry for supercritical water reactor
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 assem...
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| Format: | Article |
| Language: | English |
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Elsevier
2019-11-01
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| Series: | Heliyon |
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| Online Access: | http://www.sciencedirect.com/science/article/pii/S2405844019365867 |
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| author | Seth Kofi Debrah Edward Shitsi Silas Chabi Neda Sahebi |
| author_facet | Seth Kofi Debrah Edward Shitsi Silas Chabi Neda Sahebi |
| author_sort | Seth Kofi Debrah |
| collection | DOAJ |
| description | 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. |
| first_indexed | 2024-12-11T00:39:19Z |
| format | Article |
| id | doaj.art-36e950e04ec14f139274de558a65b85b |
| institution | Directory Open Access Journal |
| issn | 2405-8440 |
| language | English |
| last_indexed | 2024-12-11T00:39:19Z |
| publishDate | 2019-11-01 |
| publisher | Elsevier |
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| series | Heliyon |
| spelling | doaj.art-36e950e04ec14f139274de558a65b85b2022-12-22T01:26:59ZengElsevierHeliyon2405-84402019-11-01511e02927Assessment of heat transfer correlations in the sub-channels of proposed rod bundle geometry for supercritical water reactorSeth Kofi Debrah0Edward Shitsi1Silas Chabi2Neda Sahebi3Department of Nuclear Engineering, Graduate School of Nuclear and Allied Sciences, University of Ghana, P.O. Box AE 1, Kwabenya, Accra, Ghana; Ghana Atomic Energy Commission (GAEC), Nuclear Power Institute, P.O. Box LG 80, Legon-Accra, GhanaDepartment of Nuclear Engineering, Graduate School of Nuclear and Allied Sciences, University of Ghana, P.O. Box AE 1, Kwabenya, Accra, Ghana; Ghana Atomic Energy Commission (GAEC), Nuclear Power Institute, P.O. Box LG 80, Legon-Accra, Ghana; Corresponding author.Department of Nuclear Engineering, Graduate School of Nuclear and Allied Sciences, University of Ghana, P.O. Box AE 1, Kwabenya, Accra, GhanaInstitute of Nuclear Energy Safety Technology, CAS, FDS Team, P.O Box 1135, No. 350, Hefei, Anhui, 230031, ChinaThere 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.http://www.sciencedirect.com/science/article/pii/S2405844019365867MathematicsMechanical engineeringNuclear engineeringPhysicsHeat transfer correlationsHeat transfer enhancement |
| spellingShingle | Seth Kofi Debrah Edward Shitsi Silas Chabi Neda Sahebi Assessment of heat transfer correlations in the sub-channels of proposed rod bundle geometry for supercritical water reactor Heliyon Mathematics Mechanical engineering Nuclear engineering Physics Heat transfer correlations Heat transfer enhancement |
| title | Assessment of heat transfer correlations in the sub-channels of proposed rod bundle geometry for supercritical water reactor |
| title_full | Assessment of heat transfer correlations in the sub-channels of proposed rod bundle geometry for supercritical water reactor |
| title_fullStr | Assessment of heat transfer correlations in the sub-channels of proposed rod bundle geometry for supercritical water reactor |
| title_full_unstemmed | Assessment of heat transfer correlations in the sub-channels of proposed rod bundle geometry for supercritical water reactor |
| title_short | Assessment of heat transfer correlations in the sub-channels of proposed rod bundle geometry for supercritical water reactor |
| title_sort | assessment of heat transfer correlations in the sub channels of proposed rod bundle geometry for supercritical water reactor |
| topic | Mathematics Mechanical engineering Nuclear engineering Physics Heat transfer correlations Heat transfer enhancement |
| url | http://www.sciencedirect.com/science/article/pii/S2405844019365867 |
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