Published 1986
| Version v1
Book
Effect of cross sectional shape on critical heat flux in a vertical tube cooled by Freon-12
Creators
- 1. Korea Advanced Energy Research Inst., Daeduk (Republic of Korea)
Description
Critical Heat Flux (CHF) measurements have been made in three subchannel shaped test sections cooled by Freon-12. The cross sections of the test sections were : round, triangular and rectangular ones. At a coolant quality of more than 10 % the effect of subchannel shape on CHF was not significant. The effect was significant, however, in the subcooled region where CHF was up to 38 % below that predicted by the W-3 tube correlation. (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. 1/22-1/26.
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
- 18061293
- Subject category
- S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COOLANT LOOPS; CRITICAL HEAT FLUX; FREONS; FUEL CHANNELS; HEAT TRANSFER; PRIMARY COOLANT CIRCUITS; SHAPE; SIMULATORS; VOID FRACTION
- Descriptors DEC
- ANALOG SYSTEMS; COOLING SYSTEMS; ENERGY TRANSFER; FUNCTIONAL MODELS; HEAT FLUX; ORGANIC COMPOUNDS; ORGANIC HALOGEN COMPOUNDS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS