Evaluation of condensation heat transfer coefficient in AC600 passive containment cooling system
Description
The author gives a warranty to choice condensation heat transfer correlation (HTC) in AC600 passive containment cooling system (PCCS) analysis by comparing some most useful condensation HTC used in PCCSAC-MD code which is a multi-dimensional thermal-hydraulic analysis code for AC600 PCCS. These correlations include Uchida correlation, Gido-Koestl correlation, Tagami correlation and heat-mass transfer analogy correlation using the heat transfer coefficient on the vapor side of the interface. The author gets the conclusion that the Uchida correlation based on steady state data of experiment is more conservative than the Gido-Koestl correlation. The difference of peak pressure value of AC600 containment under double ended cold leg loss of coolant accident or main steam line break accident calculated by different correlation is similar while for double ended hot leg loss of coolant accident the difference is big, Although different correlation gets different heat transfer coefficient. The Tagami correlation is the most conservative one in the main steam line break accident calculated
Additional details
Publishing Information
- Journal Title
- Nuclear Power Engineering
- Journal Volume
- 20
- Journal Issue
- 3
- Journal Page Range
- p. 214-218
- ISSN
- 0258-0926
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 31007460
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- CHINA; CONTAINMENT SPRAY SYSTEMS; DESIGN BASIS ACCIDENTS; EXPERIMENTAL DATA; HEAT TRANSFER; MODIFICATIONS; P CODES; PWR TYPE REACTORS; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- ACCIDENTS; ASIA; COMPUTER CODES; CONTAINMENT; CONTAINMENT SYSTEMS; DATA; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; INFORMATION; NUMERICAL DATA; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS