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PMID: 31844770 Published · epublish English Journal Article

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

Heliyon ·Vol. 5 ·No. 11 ·2019-11-00 ·页码 e02927

Debrah SK, Shitsi E, Chabi S, Sahebi N

Abstract

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.

Keywords
Heat transfer correlations Heat transfer deterioration Heat transfer enhancement Mathematics Mechanical engineering Nuclear engineering Physics Supercritical water-cooled reactor
作者与单位
共 4 位作者,点击展开单位 / ORCID
Debrah Seth Kofi
Department 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.
Shitsi Edward
Department 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.
Chabi Silas
Department of Nuclear Engineering, Graduate School of Nuclear and Allied Sciences, University of Ghana, P.O. Box AE 1, Kwabenya, Accra, Ghana.
Sahebi Neda
Institute of Nuclear Energy Safety Technology, CAS, FDS Team, P.O Box 1135, No. 350, Hefei, Anhui, 230031, China.
Article Info
Journal
Heliyon
Abbr.
Heliyon
ISSN
2405-8440
Published
2019-11-00
电子出版
2019-00-27
页码
e02927
Language
English
Country/Region
England
NLM ID
101672560
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