Numerical simulation on the saturated pool boiling on a downward facing hemispherical
Creators
- 1. School of Energy and Power Engineering, Chongqing University, Chongqing (China)
- 2. State Nuclear Power Technology Research & Development Center, Beijing (China)
- 3. College of Aerospace Engineering, Chongqing University, Chongqing (China)
Description
In the present study, a two-phase transient three-dimensional CFD simulation is carried out to numerically investigate the saturated downward facing pool boiling on a hemispherical heating surface. This simulation is performed within the OpenFOAM framework and the Volume of Fluid (VOF) model has been chosen in this research. This code can be used to predict the distribution of the local flow parameters, such as the void fraction, bubble diameter, the velocity of both liquid and gas, the turbulent intensity as well as liquid temperature. Special attention has been devoted to the two phase flow characteristics and vapor morphology along the overheated hemispherical curved surface. For the validation of boiling phenomena, the results of CFD simulation are compared with the visualizations of subscale boundary layer boiling experiment conducted by State Nuclear Power Technology Research & Development Center (SNPTRD) in China. Simulation results show that vapor behavior along the hemispherical curved surface is cyclical, repeatedly forming a stratified vapor layer at the bottom center, which stretches as more vapor is generated, and then flows upwards along from the convex surface. These numerical results show good agreements with the experimental data. Moreover, detailed analysis focusing on the pressure, velocity, void fraction, heating wall temperature as well as the two phase natural circulation flow characteristics are proposed in this paper. It is found that the vapor behavior of downward facing pool boiling on a hemispherical surface is quite different from those on other surface orientations in many respects including the bubble shape, velocity, rise distance and moving trajectory. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the 27th international conference on nuclear engineering (ICONE-27)
- Imprint Pagination
- [4028 p.]
- Journal Page Range
- 6 p.
Conference
- Title
- 27. international conference on nuclear engineering
- Acronym
- ICONE-27
- Dates
- 19-24 May 2019
- Place
- Tsukuba, Ibaraki (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 51011515
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ACCIDENT MANAGEMENT; COMPUTERIZED SIMULATION; CRITICAL HEAT FLUX; FLUID MECHANICS; HEAT TRANSFER; NUCLEAR POWER PLANTS; POOL BOILING; REACTOR SAFETY; REACTOR VESSELS; SEVERE ACCIDENTS; SPECIFIC HEAT; THERMAL CONDUCTIVITY; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; BOILING; CONTAINERS; ENERGY TRANSFER; FLUID FLOW; HEAT FLUX; MANAGEMENT; MECHANICS; NUCLEAR FACILITIES; PHASE TRANSFORMATIONS; PHYSICAL PROPERTIES; POWER PLANTS; SAFETY; SIMULATION; THERMAL POWER PLANTS; THERMODYNAMIC PROPERTIES
Optional Information
- Notes
- Available as Internet Data in PDF format, Folder Name: Track08, Paper ID: ICONE27-1440F.pdf; 12 refs., 5 figs.