Published December 2012
| Version v1
Journal article
Study on application of CHF models on reactor pressure vessel lower head for severe accident condition
- 1. Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu (China)
- 2. Department of Nuclear Science and Technology, Xi'an Jiaotong University (China)
Description
According to the in-vessel retention (IVR) mitigation and the heat transfer characteristics, two theoretical models for predicting the critical heat flux (CHF), the interfacial lift-off theoretical model and the theoretical model considering the hydrodynamic behavior of the vapor-liquid interface of a bubble, are modified, respectively, and a general CHF model is developed to analyze the lower head CHF. The results indicate that the CHF model could well predict the experimental data on large scale curved surface. (authors)
Additional details
Publishing Information
- Journal Title
- Nuclear Power Engineering
- Journal Volume
- 33
- Journal Issue
- 6
- Journal Page Range
- p. 46-50
- ISSN
- 0258-0926
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 45102897
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- BUBBLES; CRITICAL HEAT FLUX; DIAGRAMS; EXPERIMENTAL DATA; HEAD; HEAT TRANSFER; HYDRODYNAMICS; INTERFACES; LIQUIDS; MITIGATION; PRESSURE VESSELS; REACTOR ACCIDENTS; RETENTION; VAPORS
- Descriptors DEC
- ACCIDENTS; BODY; CONTAINERS; DATA; ENERGY TRANSFER; FLUID MECHANICS; FLUIDS; GASES; HEAT FLUX; INFORMATION; MECHANICS; NUMERICAL DATA
Optional Information
- Notes
- 5 figs., 12 refs.