The effect of flow from below on dryout heat flux
Journal Article
·
· Journal of Heat Transfer (Transactions of the ASME (American Society of Mechanical Engineers), Series C); (United States)
- Univ. of California, Los Angeles (United States)
An experimental investigation of dryout heat flux in a saturated porous medium with forced flow from below has been conducted. Freon-113, methanol, and water were used as test fluids. Particle sizes were 0.59-0.79 mm, 1.6 mm, 3.2 mm, and 4.8 mm. The dryout heat flux increases as the inlet mass flux increases, and asymptotically approaches the total evaporation energy of the inlet flow. The pressure drop across the bed changes rapidly near the dryout point due to the formation of a dry zone.
- OSTI ID:
- 6032403
- Journal Information:
- Journal of Heat Transfer (Transactions of the ASME (American Society of Mechanical Engineers), Series C); (United States), Journal Name: Journal of Heat Transfer (Transactions of the ASME (American Society of Mechanical Engineers), Series C); (United States) Vol. 109:2; ISSN 0022-1481; ISSN JHTRA
- Country of Publication:
- United States
- Language:
- English
Similar Records
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Journal Article
·
Fri Dec 31 23:00:00 EST 1982
· AIChE Symp. Ser.; (United States)
·
OSTI ID:5453089
Further studies of degraded core coolability: The effect of pressure and coolant flow from below: Interim report
Technical Report
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Fri Oct 31 23:00:00 EST 1986
·
OSTI ID:7037589
Dryout heat flux in a volumetrically heated porous bed
Thesis/Dissertation
·
Wed Dec 31 23:00:00 EST 1986
·
OSTI ID:5747997
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
ACCIDENTS
CONVECTION
CRITICAL HEAT FLUX
DATA
ENERGY TRANSFER
EXPERIMENTAL DATA
FORCED CONVECTION
HEAT FLUX
HEAT TRANSFER
INFORMATION
LOSS OF COOLANT
MASS TRANSFER
MATERIALS
NUMERICAL DATA
POROUS MATERIALS
REACTOR ACCIDENTS
REACTORS
WATER COOLED REACTORS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
ACCIDENTS
CONVECTION
CRITICAL HEAT FLUX
DATA
ENERGY TRANSFER
EXPERIMENTAL DATA
FORCED CONVECTION
HEAT FLUX
HEAT TRANSFER
INFORMATION
LOSS OF COOLANT
MASS TRANSFER
MATERIALS
NUMERICAL DATA
POROUS MATERIALS
REACTOR ACCIDENTS
REACTORS
WATER COOLED REACTORS