One-dimensional model analysis of flow circulation and thermal stratification in AP1000 containment
- 1. Beijing Key Laboratory of Passive Nuclear Safety Technology, School of Nuclear Science and Engineering, North China Electric Power University, Beijing (China)
- 2. Shanghai Nuclear Engineering Research and Design Institute, Shanghai (China)
- 3. State Nuclear Power Technology R and D Center, Beijing (China)
Description
Passive containment cooling system is one of the important safety systems in AP1000. The heat produced in the containment can be transferred to the atmosphere based on natural circulation both in the containment and in the air flow channel outside the containment. The flow circulation and thermal stratification in the large volume of the containment have essential effect on the flow and heat transfer. In this paper, one- dimensional thermal-hydraulic model was established based on stratification theory for the natural circulations in and outside the steel containment. The calculation efficiency was improved and the temperature distribution was obtained. By comparing with the result of the three-dimensional model, the rationality of the one-dimensional model was verified. The pressure and constituent distributions in the containment were also calculated. (authors)
Additional details
Identifiers
Publishing Information
- Journal Title
- Atomic Energy Science and Technology
- Journal Volume
- 48
- Journal Issue
- 10
- Journal Page Range
- p. 1803-1806
- ISSN
- 1000-6931
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 48088652
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AIR FLOW; CONTAINMENT; COOLING SYSTEMS; EFFICIENCY; HEAT; NATURAL CONVECTION; ONE-DIMENSIONAL CALCULATIONS; PRESSURE DEPENDENCE; PWR TYPE REACTORS; SAFETY; STRATIFICATION; TEMPERATURE DISTRIBUTION; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- CONVECTION; ENERGY; ENERGY SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; FLUID MECHANICS; GAS FLOW; HEAT TRANSFER; HYDRAULICS; MASS TRANSFER; MECHANICS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 4 figs., 9 refs.; http://dx.doi.org/10.7538/yzk.2014.48.10.1803