Heat transfer characteristics of an annulus channel cooled with R-134a fluid near the critical pressure
- 1. KAERI, Taejon (Korea, Republic of)
Description
An experimental study on heat transfer characteristics near the critical pressure has been performed with an internally-heated vertical annular channel cooled by R-134a fluid. Two series of tests have been completed: (a) steady-state critical heat flux (CHF) and (b) heat transfer tests for pressure reduction transients through the critical pressure. In the present experimental range, the steady-state CHF decreases with the increase of the system pressure. For a fixed inlet mass flux and subcooling, the CHF falls sharply at about 3.8 MPa and shows a trend toward converging to zero as the pressure approaches the critical point of 4.059 MPa. The CHF phenomenon near the critical pressure does not lead to an abrupt temperature rise of the heated wall because the CHF occurred at remarkably low power levels. In the pressure reduction transient experiments, as soon as the pressure passed through the critical pressure, the wall temperatures rise rapidly up to a very high value due to the occurrence of the departure from nucleate boiling. The wall temperature reaches a maximum at the saturation point of the outlet temperature, then tends to decrease gradually
Additional details
Publishing Information
- Publisher
- KSME
- Imprint Place
- Seoul (Korea, Republic of)
- Imprint Title
- Proceedings of the KSME 2004 spring annual meeting
- Imprint Pagination
- [CD-ROM]
- Journal Page Range
- [6 p.]
Conference
- Title
- 2004 spring annual meeting of the KSME
- Dates
- 28-30 Apr 2004
- Place
- Pyeongchang (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 35090052
- Subject category
- S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ANNULAR SPACE; CRITICAL HEAT FLUX; CRITICAL PRESSURE; HEAT TRANSFER; NUCLEATE BOILING; REACTOR CHANNELS; REACTOR SAFETY EXPERIMENTS; REACTORS; SUPERCRITICAL STATE; TRANSIENTS
- Descriptors DEC
- BOILING; CONFIGURATION; ENERGY TRANSFER; HEAT FLUX; PHASE TRANSFORMATIONS; PHYSICAL PROPERTIES; REACTOR COMPONENTS; SPACE; THERMODYNAMIC PROPERTIES
Optional Information
- Notes
- 9 refs, 8 figs, 1 tab