On the Application of CFD Modeling for the Prediction of the Degree of Mixing in a PWR During a Boron Dilution Transient
Creators
- 1. NRG, Plant Performance and Technology, Westerduinweg 3, P.O. Box 25, 1755 ZG Petten (Netherlands)
- 2. Research Center Rossendorf (Netherlands)
Description
In a Pressurized Water Reactor, negative reactivity is present in the core by means of Boric acid as a soluble neutron absorber in the coolant water. During a so-called Boron Dilution Transient (BDT), a de-borated slug of coolant water is transported from the cold leg into the reactor vessel, and the borated coolant water is diluted by mixing with this un-borated water. The resulting decrease in the boron concentration leads to an insertion of positive reactivity in the core, which may lead to a reactivity excursion. The associated power peak may damage the fuel rods. The mixing of borated and un-borated water in downcomer and lower plenum is an important process, because it mitigates the degree of reactivity insertion. In the present study the application of Computational Fluid Dynamics (CFD) for the prediction of this mixing of un-borated with borated water in the RPV has been assessed. The analyses have been compared with the measurement data from the Rossendorf coolant mixing model (ROCOM) experiment. The ROCOM test facility represents the primary cooling system of a KONVOI type of PWR (1300 MWel). In spite of the complicated spatial, temporal, and geometrical aspects of the flow in the RPV, the agreement between the calculated and the experimental data is good. The CFD model tends to slightly under predict the degree of mixing in the RPV resulting in a slight under-prediction of the boron concentration at the core. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 0-89448-698-5
- Imprint Title
- Proceedings of the 2006 international congress on advances in nuclear power plants - ICAPP'06
- Imprint Pagination
- 2734 p.
- Journal Page Range
- p. 1646-1655
Conference
- Title
- 2006 International congress on advances in nuclear power plants - ICAPP'06
- Dates
- 4-8 Jun 2006
- Place
- Reno - Nevada (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 39042796
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BORIC ACID; COMPUTERIZED SIMULATION; COOLANTS; DILUTION; EXCURSIONS; FLUID MECHANICS; FORECASTING; FUEL RODS; NEUTRON ABSORBERS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTIVITY; REACTIVITY INSERTIONS; REACTOR VESSELS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; BORON COMPOUNDS; CONTAINERS; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; HYDROGEN COMPOUNDS; INORGANIC ACIDS; INORGANIC COMPOUNDS; MECHANICS; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 7 refs.