Three-dimensional compressible two-fluid model and its application
- 1. Hitachi, Ltd., Power and Industrial Systems R and D Laboratory (Japan)
- 2. Hitachi, Ltd., Nuclear Systems Division (Japan)
Description
Reliable prediction of the behavior of a compressible gas-liquid two-phase flow is important for the integrity assessment of power plants. A numerical method for the extended two-fluid model for highly compressible gas-liquid two-phase flow has been developed. The extended two-fluid model can treat the behavior of the interface between gas and liquid because of its accurate discontinuous void fraction transport calculations. The Riemann invariance, related to discontinuities of pressure and velocity in compressible flow, is taken into consideration by the Godunov scheme, originally developed for single-phase compressible flow. The numerical method was implemented in a computer program which was applied to predict integrity of the suppression pool structures during operation of SRVs (Safety Relief Valves) in BWRs (Boiling Water Reactors). If the pressure of the RPV (Reactor Pressure Vessel) becomes higher, SRVs are opened and excessive gas flows into the exhaust pipes to the suppression pool. The present method was applied to predict the transient pressure field caused by large bubble oscillation near the quencher site in the suppression pool. The results showed that the peak pressure changed according to the depth of water in the pool and the pressure propagation was attenuated as time passed. (authors)
Additional details
Publishing Information
- Publisher
- Atomic Energy Press
- Imprint Place
- Beijing (China)
- ISBN
- 7-5022-3400-4
- Imprint Title
- The 13th international conference on nuclear engineering abstracts
- Imprint Pagination
- 604 p.
- Journal Page Range
- p. 399-400
Conference
- Title
- 13. international conference on nuclear engineering
- Dates
- 16-20 May 2005
- Place
- Beijing (China)
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 38036673
- Subject category
- S99: GENERAL AND MISCELLANEOUS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COMPRESSIBLE FLOW; COMPUTER CODES; GAS FLOW; LIQUID FLOW; NUMERICAL ANALYSIS; PRESSURE DEPENDENCE; PRESSURE SUPPRESSION; RELIEF VALVES; RIEMANN FUNCTION; THREE-DIMENSIONAL CALCULATIONS; TRANSIENTS; TWO-PHASE FLOW; USES; VOID FRACTION
- Descriptors DEC
- CONTROL EQUIPMENT; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; FLUID FLOW; FUNCTIONS; MATHEMATICS; POWER REACTORS; REACTORS; THERMAL REACTORS; VALVES; WATER COOLED REACTORS; WATER MODERATED REACTORS