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)
Files
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)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 43084133
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COOLANTS; CORRELATIONS; FAST REACTORS; HEAT TRANSFER; LIQUID METAL COOLED REACTORS; MODERATORS; SAFETY ANALYSIS; SECONDARY COOLANT CIRCUITS; SUPERCRITICAL STATE; T CODES; WATER COOLED REACTORS; WORKING FLUIDS
- Descriptors DEC
- COMPUTER CODES; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; EPITHERMAL REACTORS; FLUIDS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS
Optional Information
- Notes
- Available as CD-ROM Data in PDF format, Folder Name: FinalPaper, Paper ID: 9134.pdf; 26 refs., 3 figs., 2 tabs.