CFD simulation of fibre material transport in a PWR core under loss of coolant conditions
- 1. Forschungszentrum Dresden-Rossendorf e.V., Dresden (Germany). Inst. of Safety Research
Description
The aim of the numerical simulations carried out in this study was to determine how and where mineral wool fibres transported to the core by ECC water during a LOCA are deposited across the grid spacers of the fuel elements of a German PWR. The spacer grid is modelled as a strainer which completely retains the insulation material carried by the coolant and reaching the plane of the spacers. The accumulation of the insulation material gives rise to the formation of a compressible fibrous cake whose permeability to the coolant flow is calculated in terms of the local amount of deposited material and the local value of the superficial liquid velocity. The calculations showed that the fiber material at the uppermost spacer grid plane is not evenly distributed. First, it is accumulated at the positions of the break-through channels. Later when the inner circulation in the core has stopped, the insulation material can also be distributed into other regions of the spacer plane. Further investigations are necessary to determine the accumulation of insulation material for a longer period of time. Also steam production in the core or re-suspension of the insulation material during back flow should be considered. Moreover, the geometry modeling should be improved taking into account the real structures in the upper plenum and the geometry of the ECC injection nozzle ('Hutze'). (orig.)
Additional details
Additional titles
- Original title (English)
- Jahrestagung Kerntechnik 2010. Dokumentation
Publishing Information
- Publisher
- Inforum Verlag
- Imprint Place
- Bonn (Germany)
- Imprint Title
- Annual meeting on nuclear technology 2010. Documentation
- Imprint Pagination
- 1017 p.
- Journal Page Range
- 6 p.
Conference
- Title
- Annual meeting on nuclear technology 2010
- Original Conference Title
- Jahrestagung Kerntechnik 2010
- Dates
- 4-6 May 2010
- Place
- Berlin (Germany)
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 43018443
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; BOUNDARY CONDITIONS; BUILDUP; COMPUTERIZED SIMULATION; CORROSION PRODUCTS; ECCS; FIBERS; FLUID FLOW; FLUID MECHANICS; LOSS OF COOLANT; MASS TRANSFER; MINERAL WOOL; PRESSURE VESSELS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR CORES; REACTOR VESSELS; SAFETY INJECTION; SPACERS
- Descriptors DEC
- ACCIDENTS; CONTAINERS; COOLING SYSTEMS; ENERGY SYSTEMS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; MECHANICS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR PROTECTION SYSTEMS; REACTORS; REMOVAL; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Jahrestagung Kerntechnik 2010. Dokumentation