Numerical simulation of thermal stratification in cold legs by using OpenFOAM
Description
During a small-break loss-of-coolant accident in pressurized water reactors (PWRs), emergency core cooling system (ECCS) is actuated and cold water is injected into cold legs. Insufficient mixing of injected cold water and hot primary coolant results in thermal stratification, which is a matter of concern for evaluation of pressurized thermal shock (PTS) in view of aging and life extension of nuclear power plants. In this study, an open source CFD software, OpenFOAM, is used to simulate mixing and thermal stratification in the cold leg of ROSA/LSTF, which is the largest thermal-hydraulic integral test facility simulating PWR. One of the cold-leg is numerically simulated from the outlet of primary coolant pump to the inlet of downcomer. ECCS water is injected from injection nozzle connected at the top of the cold leg into the steady-state natural circulation flow under high-pressure and high-temperature conditions. The temperature distribution in the cold leg is compared with experimental and FLUENT's results. Effects of turbulent flow models and secondary flow due to the elbow section of the cold leg are discussed for the case with the single-phase natural circulation. Injection into a two-phase stratified flow is also simulated and predictive and numerical capabilities of OpenFOAM are discussed. (author)
Availability note (English)
Available from http://dx.doi.org/10.15669/pnst.2.107Additional details
Identifiers
- DOI
- 10.15669/pnst.2.107;
Publishing Information
- Journal Title
- Progress in Nuclear Science and Technology
- Journal Volume
- 2
- Journal Page Range
- p. 107-113
- ISSN
- 2185-4823
Conference
- Title
- Joint international conference of the 7th supercomputing in nuclear application and the 3rd Monte Carlo
- Acronym
- SNA+MC 2010
- Dates
- 17-21 Oct 2010
- Place
- Tokyo (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 49052006
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; COMPUTERIZED SIMULATION; ECCS; NATURAL CONVECTION; PWR TYPE REACTORS; REACTOR ACCIDENT SIMULATION; REACTOR SAFETY; SBLOCA; STRATIFICATION; SUPERCOMPUTERS; TEMPERATURE DISTRIBUTION; THERMAL HYDRAULICS; THERMAL SHOCK; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; COMPUTERS; CONVECTION; DIGITAL COMPUTERS; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID FLOW; FLUID MECHANICS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; MASS TRANSFER; MECHANICS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 10 refs., 16 figs., 2 tabs.