Critical heat flux at low velocity and pressure conditions
Creators
- 1. Kyoto Univ., Kumatori, Osaka (Japan). Research Reactor Inst.
Description
The purpose of this study is to provide some systematic understanding on critical heat flux (CHF) at low velocity and pressure conditions in which the effects of gravity and flow instability are remarkable. Experimental data obtained previously for water in an annulus, rectangular ducts and a round tube are briefly reviewed and augmented in collaboration with existing data and correlations to extract more generic information. The effect of channel geometry is then discussed. The effect of channel geometry turned out to be significant at intermediate mass velocities. The difference in CHF at these mass velocities between a round tube and the other channel geometries was attributed mainly to the existence of unheated wall which causes a nonuniform distribution of liquid film. (author)
Additional details
Publishing Information
- Publisher
- Atomic Energy Soc. of Japan.
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- Proceedings of second international topical meeting on nuclear power plant thermal hydraulics and operations
- Imprint Pagination
- 1191 p.
- Journal Page Range
- p. 1/1-1/8.
Conference
- Title
- 2. international topical meeting on nuclear power plant thermal hydraulics and operations.
- Dates
- 15-17 Apr 1986.
- Place
- Tokyo (Japan).
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 18061291
- Subject category
- S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COOLANT LOOPS; CRITICAL HEAT FLUX; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; PRIMARY COOLANT CIRCUITS; THERMODYNAMICS; VELOCITY
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; ENERGY TRANSFER; HEAT FLUX; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS