Coolability of volumetrically heated particle beds
Description
In case of a severe nuclear reactor accident, with loss of coolant, a particle bed may be formed from the fragmentation of the molten core in the residual water at different stages of the accident. To avoid further propagation of the accident and maintain the integrity of the reactor pressure vessel, the decay heat of the particle bed must be removed. To better understand the various thermo-hydraulic processes within such heat-generating particle beds, the existing DEBRIS test facility at IKE has been modified to be able to perform novel boiling, dryout and quenching experiments. The essential experimental data includes the pressure gradients measured by 8 differential pressure transducers along the bed height as a function of liquid and vapour superficial velocities, the determination of local dryout heat fluxes for different system pressures as well as the local temperature distribution measured by a set of 51 thermocouples installed inside the particle bed. The experiments were carried out for two different particle beds: a polydispersed particle bed which consisted of stainless steel balls (2 mm, 3 mm and 6 mm diameters) and an irregular particle bed which consisted of a mixture of steel balls (3 mm and 6 mm) and irregularly shaped Al2O3 particles. Additionally, all experiments were carried out for different flow conditions, such as the reference case of passive 1D top-flooding, 1D bottom flooding (driven by external pumps and different downcomer configurations) and 2D top-/bottom-/lateral flooding with a perforated downcomer. In this work, it has been observed that for both particle beds with downcomer configurations an open downcomer leads to the best coolability (dryout heat flux = 1560 kW/m2, polydispersed particle bed, psys = 1 bar) of the particle bed, mainly due to bottom-flow with enhanced natural convection. It has also been shown that a potential lateral flow via a perforation of the downcomer does not bring any further improvements in coolability. By contrast, in comparison to the open (non-perforated) downcomer the measured dryout heat flux was reduced by 40% to 956 kW/m2. However, both downcomer configurations lead to a better coolability in comparison to the reference case of pure top-flooding (dryout heat flux = 738 kW/m2). The dryout heat flux values along with the pressure-drop data can further be used for the validation of numerical models used in simulation codes.
Availability note (English)
Available from: https://elib.uni-stuttgart.de/bitstream/11682/9231/3/Dissertation_MuhammadRashid.pdfAdditional details
Identifiers
Publishing Information
- Imprint Pagination
- 135 p.
- ISSN
- 0173-6892
- Report number
- IKE--8-124
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 49007000
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Thesis, Non-conventional Literature
- Descriptors DEI
- COOLING; CORE FLOODING SYSTEMS; CORIUM; DATA COVARIANCES; DRYOUT; FRAGMENTATION; HEAT FLUX; HEAT PRODUCTION; MELTDOWN; NUMERICAL ANALYSIS; PRESSURE MEASUREMENT; PRESSURE VESSELS; QUENCHING; REACTOR ACCIDENT SIMULATION; REACTOR VESSELS; TEMPERATURE MEASUREMENT; THERMAL HYDRAULICS; THERMOCOUPLES; VALIDATION
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; CONTAINERS; CONVERSION; ECCS; ENERGY CONVERSION; ENGINEERED SAFETY SYSTEMS; FLUID MECHANICS; HYDRAULICS; MATHEMATICS; MEASURING INSTRUMENTS; MECHANICS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; SEVERE ACCIDENTS; SIMULATION; TESTING