Experimental results on the coolability of a debris bed with multidimensional cooling effect
- 1. Institute for Nuclear Technology and Energy Systems (IKE), University of Stuttgart, Stuttgart (Germany)
- 2. Reactor Engineering Division, Bhabha Atomic Research Centre, Mumbai (India)
Description
Within the reactor safety research, the removal of decay heat from a debris bed (formed from corium and residual water) is of great importance. In order to investigate experimentally the long term coolability of debris beds, the scaled test facility 'DEBRIS' has been built at IKE. A large number of experiments had been carried out to investigate the coolability limits for different bed configurations. Analyses based on one-dimensional configurations underestimate the coolability in realistic multidimensional configurations, where lateral water access and water inflow via bottom regions are favoured. Following the experiments with top- and forced bottom-flooding flow conditions this paper presents experimental results of boiling and dryout tests at different system pressures based on top- and bottom-flooding via a down comer configuration. A down comer with an internal diameter of 10 mm has been installed at the centre of the debris bed. The debris bed is built up in a cylindrical crucible with an inner diameter of 125 mm. The bed of height 640 mm is composed of polydispersed particles with particle diameters 2, 3 and 6 mm. Since the long term coolability of such particle bed is limited by the availability of coolant inside the bed and not by heat transfer limitations from the particles to the coolant, the bottom inflow of water improves the coolability of the debris bed and an increase of the dryout heat flux can be observed. The system pressure has no significant effect on the pressure gradient inside the bed. With increasing system pressure, the coolability limits are enhanced (dryout heat flux). (author)
Additional details
Publishing Information
- Imprint Title
- NURETH-13: Proceedings of the 13th international topical meeting on nuclear reactor thermal hydraulics
- Imprint Pagination
- [4617 p.]
- Journal Page Range
- [11 p.]
Conference
- Title
- 13. international topical meeting on nuclear reactor thermal hydraulics
- Acronym
- NURETH-13
- Dates
- 27 Sep - 2 Oct 2009
- Place
- Kanazawa, Ishikawa (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 43036650
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AFTER-HEAT REMOVAL; BOILING; CONFIGURATION; COOLING; CORIUM; DRYOUT; HEAT FLUX; HEAT TRANSFER; PRESSURE DROP; REACTOR SAFETY; TEMPERATURE DISTRIBUTION; WATER COOLED REACTORS
- Descriptors DEC
- ENERGY TRANSFER; PHASE TRANSFORMATIONS; REACTORS; REMOVAL; SAFETY
Optional Information
- Notes
- Available as CD-ROM Data in PDF format, Folder Name: FullPaper, Paper ID: N13P1148.pdf