Investigation Of Conditions For Zinc Particle Release And Transport In The Reactor Core

PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 4(2014)

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Abstract
Background of the experimental and methodical work is a loss of coolant accident (LOCA) in a Pressurized Water Reactor (PWR). During LOCA, both the leakage water jet as well as the water in the containment can lead to corrosion of galvanized installations (e.g. grates). That means a change of consistency and chemical properties of the coolant water during the sump recirculation operation, in particular an increase of the zinc concentration (Zn2+ ions in dissolution) and the pH-value. Furthermore, it leads to separation of layer-forming zinc compounds (e.g. zinc borate) at hotspots (fouling at fuel assemblies) and/or the crystallization of zinc corrosion products out of the coolant in hot areas [HOF10]. This in turn causes a decrease of pH-value and, consequently, an increase of the corrosiveness of the coolant flow. This can come along with a chemical transformation of zinc borate to nearly indissoluble zinc oxide by thermo hydrolysis. Spalling parts of the coating on the surface of the fuel rods could lead to the release of particles into coolant water flow. In combination with the release of fibrous insulation material, which can be transported into the reactor containment, containment building sump and connected systems, this process causes pressure build-ups at the strainers and the spacers of the fuel assemblies and a reduction of the pump performance. In this case, efficient heat dissipation cannot be guaranteed.In a joint research project between the Institnte of Process Technology, Process Automation and Measuring Technology (IPM) of University Zittau/Goerlitz and the Helmholtz-Zentrum Dresden-Rossendorf (HZDR), the influence of different boundary conditions like the flow structures in the reactor pressure vessel, temperature distributions and the temperature gradient in the central core regions will be investigated. Therefore, in a final step a test facility containing a 3x3 heated fuel rod dummy configuration was designed and constructed. The design and development of the test facility was accompanied by pre-test calculations and CFD simulations to get information about local surface and fluid temperatures under different flow conditions.
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Key words
Reactor safety,Loss of coolant accident,Zinc corrosion,Experiments,Fuel assembly
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