Comparison of heat transfer models with databank of supercritical fluid
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M. Zhao
Abstract
Because of the large variation of thermal–physical properties near pseudo-critical point, heat transfer of supercritical water shows abnormal behavior. Thus, an accurate prediction of heat transfer between the cladding and fluid plays a very important role. It is necessary to investigate the reliably of heat transfer models in the vicinity of the pseudo-critical point. In the frame of evaluating the present HT models and developing new reliable prediction models, databank of heat transfer of supercritical water flowing in tube were established by Karlsruhe Institute of Technology (KIT) with more than 35,000 experimental data. A thorough analysis and assessment was carried out, to give an insight into the characters of the database. Experimental data from different sources are compared to figure out the deviation between different sources and to present the reliability of the database.
Kurzfassung
Aufgrund der großen Veränderung der thermisch-physikalischen Eigenschaften nahe dem pseudokritischen Punkt zeigt die Wärmeübertragung von überkritischem Wasser ein abnormales Verhalten. Daher spielt eine genaue Vorhersage des Wärmeübergangs zwischen dem Hüllrohr und der Flüssigkeit eine sehr wichtige Rolle. Es ist notwendig, die Zuverlässigkeit von Wärmeübertragungsmodellen in der Nähe des pseudokritischen Punktes zu untersuchen. Im Rahmen der Evaluierung der vorliegenden HT-Modelle und der Entwicklung neuer zuverlässiger Vorhersagemodelle wurde vom Karlsruher Institut für Technologie (KIT) eine Datenbank zur Wärmeübertragung von überkritischem Wasser im Rohr mit mehr als 35 000 experimentellen Daten aufgebaut. Eine gründliche Analyse und Bewertung wurde durchgeführt, um einen Einblick in den Charakter der Datenbank zu geben. Experimentelle Daten aus verschiedenen Quellen werden verglichen, um die Abweichung zwischen verschiedenen Quellen zu ermitteln und die Zuverlässigkeit der Datenbank darzustellen.
References
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© 2018, Carl Hanser Verlag, München
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Editorial
- 2nd Sino-German Symposium on Fundamentals of Advanced Nuclear Safety Technology
- Technical Contributions/Fachbeiträge
- Challenging issues and recent R&D activities for enhancing nuclear safety in Korea
- Necessary improvements of the GRS simulation chain for the simulation of light-water-cooled SMRs
- Scaling analysis of core pressure drop in reduced height integral test facility
- Criteria and comparison of thermal stratification between PRHR HX heating and ADS spraying process in IRWST based on a down-scaled experimental facility
- Numerical simulation of bubble growth on and departure from the heated surface by an improved lattice Boltzmann model
- Improvements of interfacial friction and heat transfer models for rectangular narrow channel reflood simulation based on RELAP5
- Proposal of a novel CHF correlation for PWR under low pressure conditions based on stepwise regression method
- Mechanistic prediction of post dryout heat transfer and rewetting
- Investigation of condensation process at COSMEA test facility with ATHLET code
- Research on thermal-hydraulic behavior in the spent fuel pool using a full-height experimental facility
- Experimental investigation on the distribution of spray water in a spent fuel-assembly simulator
- Wet resuspension modelling and validation
- Analysis code development for the direct reactor auxiliary cooling system of the pool-type sodium-cooled fast reactor
- Comparison of heat transfer models with databank of supercritical fluid
- Blankets – key element of a fusion reactor – functions, design and present state of development
- Preliminary steady and transient analysis for the CFETR helium cooled solid blanket system with RELAP
- A methodology for thermo-mechanical assessment of in-box LOCA events on fusion blankets and its application to EU DEMO HCPB breeding blanket
