Published 2009 | Version v1
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Assessment of heat transfer correlations for supercritical water in the frame of best-estimate code validation

  • 1. Forschungszentrum Karlsruhe GmbH, Inst. for Reactor Safety, Eggenstein-Leopoldshafen (Germany)
  • 2. Faculty of Engineering Sciences, University of Applied Sciences Wiesbaden, Ruesselsheim (Germany)
  • 3. Technical Univ. of Dresden, Inst. of Power Engineering, Dresden (Germany)

Description

Within the frame of the Generation IV international forum six innovative reactor concepts are the subject of comprehensive investigations. In some projects supercritical water will be considered as coolant, moderator (as for the High Performance Light Water Reactor) or secondary working fluid (one possible option for Liquid Metal-cooled Fast Reactors). Supercritical water is characterized by a pronounced change of the thermo-physical properties when crossing the pseudo-critical line, which goes hand in hand with a change in the heat transfer (HT) behavior. Hence, it is essential to estimate, in a proper way, the heat-transfer coefficient and subsequently the wall temperature. The scope of this paper is to present and discuss the activities at the Institute for Reactor Safety (IRS) related to the implementation of correlations for wall-to-fluid HT at supercritical conditions in Best-Estimate codes like TRACE as well as its validation. It is important to validate TRACE before applying it to safety analyses of HPLWR or of other reactor systems. In the past 3 decades various experiments have been performed all over the world to reveal the peculiarities of wall-to-fluid HT at supercritical conditions. Several different heat transfer phenomena such as HT enhancement (due to higher Prandtl numbers in the vicinity of the pseudo-critical point) or HT deterioration (due to strong property variations) were observed. Since TRACE is a component based system code with a finite volume method the resolution capabilities are limited and not all physical phenomena can be modeled properly. But Best -Estimate system codes are nowadays the preferred option for safety related investigations of full plants or other integral systems. Thus, the increase of the confidence in such codes is of high priority. In this paper, the post-test analysis of experiments with supercritical parameters will be presented. For that reason various correlations for the HT, which considers the characteristics of supercritical water, will be implemented into the TRACE source code and will be validated against selected values of various experiments. In addition, the development of a mapping scheme which selects the best suitable HT correlation depending on different parameters (mass flux, heat flux, pressure, bulk enthalpy and diameter) will be pursued. (author)

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Part of:
Proceedings of 2009 international congress on advances in nuclear power plants

Additional details

Publishing Information

Imprint Title
Proceedings of 2009 international congress on advances in nuclear power plants
Imprint Pagination
[2572 p.]
Journal Page Range
[13 p.]
Report number
INIS-JP--123

Conference

Title
2009 international congress on advances in nuclear power plants
Acronym
ICAPP2009
Dates
10-14 May 2009
Place
Tokyo (Japan)

Optional Information

Notes
Available as CD-ROM Data in PDF format, Folder Name: FinalPaper, Paper ID: 9134.pdf; 26 refs., 3 figs., 2 tabs.