Two-phase flow characteristic of inverted bubbly, slug, and annular flow in post-critical heat flux region
Description
Inverted annular flow can be visualized as a liquid jet-like core surrounded by a vapor annulus. While many analytical and experimental studies of heat transfer in this regime have been performed, there is very little understanding of the basic hydrodynamics of the post-critical heat flux (CHF) flow field. However, a recent experimental study was done that was able to successfully investigate the effects of various steady-state inlet flow parameters on the post-CHF hydrodynamics of the film boiling of a single phase liquid jet. This study was carried out by means of a visual photographic analysis of an idealized single phase core inverted annular flow initial geometry (single phase liquid jet core surrounded by a coaxial annulus of gas). In order to extend this study, a subsequent flow visualization of an idealized two-phase core inverted annular flow geometry (two-phase central jet core, surrounded by a coaxial annulus of gas) was carried out. The objective of this second experimental study was to investigate the effect of steady-state inlet, pre-CHF two-phase jet core parameters on the hydrodynamics of the post-CHF flow field. In actual film boiling situations, two-phase flows with net positive qualities at the CHF point are encountered. Thus, the focus of the present experimental study was on the inverted bubbly, slug, and annular flow fields in the post dryout film boiling region. Observed post dryout hydrodynamic behavior is reported. A correlation for the axial extent of the transition flow pattern between inverted annular and dispersed droplet flow (the agitated regime) is developed. It is shown to depend strongly on inlet jet core parameters and jet void fraction at the dryout point
Additional details
Publishing Information
- Imprint Title
- Sixteenth water reactor safety information meeting. Proceedings: Volume 4, Code uncertainty for ECCS rule; international code assessment program; thermal hydraulics; 2D/3D data applications
- Imprint Pagination
- 606 p.
- Journal Page Range
- p. 387-411.
- Report number
- NUREG/CP--0097-Vol.4
Conference
- Title
- 16. water reactor safety information meeting.
- Dates
- 24-27 Oct 1988.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20085838
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BUBBLES; BWR TYPE REACTORS; CORE FLOODING SYSTEMS; CRITICAL HEAT FLUX; DRYOUT; FILM BOILING; FLOW RATE; FLUID FLOW; GAS FLOW; HEAT TRANSFER; HYDRODYNAMICS; JETS; LIQUID FLOW; PHASE TRANSFORMATIONS; PHOTOGRAPHY; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR CORES; REACTOR SAFETY EXPERIMENTS; RESEARCH PROGRAMS; SIMULATION; STEADY-STATE CONDITIONS; TEST FACILITIES; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; BOILING; ECCS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HEAT FLUX; MECHANICS; POWER REACTORS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-8810155--Vol.4.