Heat transfer in vertical pipe flow at supercritical pressures of water
Description
A new reactor concept with light water at supercritical conditions is investigated in the framework of the European project ''High Performance Light Water Reactor'' (HPLWR). Characteristics of this reactor are the system pressure and the coolant outlet temperature above the critical point of water. Water is regarded as a single phase fluid under these conditions with a high energy density. This high energy density should be utilized in a technical application. Therefore in comparison with up to date nuclear power plants some constructive savings are possible. For instance, steam dryers or steam separators can be avoided in contrast to boiling water reactors. A thermal efficiency of about 44% can be accomplished at a system pressure of 25MPa through a water heat-up from 280 C to 510 C. To ensure this heat-up within the core reliable predictions of the heat transfer are necessary. Water as the working fluid changes its fluid properties dramatically during the heat up in the core. As such; the density in the core varies by the factor of seven. The motivation to develop a look-up table for heat transfer predications in supercritical water is due to the significant temperature dependence of the fluid properties of water. A systematic consolidation of experimental data was performed. Together with further developments of the methods to derive a look-up table made it possible to develop a look-up table for heat transfer in supercritical water in vertical flows. A look-up table predicts the heat transfer for different boundary conditions (e.g. pressure or heat flux) with tabulated data. The tabulated wall temperatures for fully developed turbulent flows can be utilized for different geometries by applying hydraulic diameters. With the developed look-up table the difficulty of choosing one of the many published correlations can be avoided. In general, the correlations have problems with strong fluid property variations. Strong property variations combined with high heat fluxes can lead to deterioration of heat transfer. This results in high wall temperatures which can reach critical values. Due to the developed understanding of the mechanisms involved in the deterioration of heat transfer, it became possible to exclude these unsafe areas for the look-up table. Comparisons of the look-up table with experimental data demonstrated a predication that exhibits a mean error of 4% with a standard deviation of 17%. The predictions of wall temperatures in supercritical water can be accurately achieved over a wide range of parameters. (orig.)
Availability note (English)
Available from TIB HannoverAdditional details
Additional titles
- Original title (German)
- Waermeuebergang von Wasser in vertikalen Rohrstroemungen bei ueberkritischem Druck
Publishing Information
- Imprint Pagination
- 173 p.
- ISSN
- 0947-8620
- Report number
- FZKA--7320
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 38082957
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Thesis, Non-conventional Literature
- Descriptors DEI
- DATA PROCESSING; DIAGRAMS; ENTHALPY; HEAT TRANSFER; PHASE TRANSFORMATIONS; PIPES; THERMAL CONDUCTIVITY; TURBULENT FLOW; TWO-PHASE FLOW; VAPOR PRESSURE; WATER; WATER COOLED REACTORS
- Descriptors DEC
- ENERGY TRANSFER; FLUID FLOW; HYDROGEN COMPOUNDS; INFORMATION; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; PROCESSING; REACTORS; THERMODYNAMIC PROPERTIES; TUBES