Critical heat fluxes of subcooled water flow boiling in a short vertical tube at high liquid Reynolds number
Creators
- 1. Institute of Advanced Energy, Kyoto University, Gokasho, Uji, Kyoto 611-0011 (Japan)
- 2. National Institute for Fusion Science, 322-6 Oroshi-cho, Toki, Gifu 509-5292 (Japan)
Description
The steady state critical heat fluxes (CHFs) and the heat transfer of the subcooled water flow boiling for the flow velocities (u = 17.2-42.4 m/s), the inlet subcoolings (ΔTsub,in = 80.9-147.6 K), the inlet pressures (Pin = 812.1-1181.5 kPa) and the exponentially increasing heat input (Q0 exp(t/τ), τ = 8.5 s) are systematically measured by the experimental water loop comprised of a new multi-stage canned-type circulation pump with high pump head. The SUS304 test tube of inner diameter (d = 6 mm), heated length (L = 59.5 mm), L/d = 9.92 and wall thickness (δ = 0.5 mm) with surface roughness (Ra = 3.18 μm) is used in this work. The steady state CHFs of the subcooled water flow boiling for the flow velocities ranging from 17.2 to 42.4 m/s are clarified. The steady state CHFs are compared with the values calculated by our transient CHF correlations against outlet and inlet subcoolings based on the experimental data for the flow velocities ranging from 4.0 to 13.3 m/s. The influence of flow velocity at high liquid Reynolds number on the subcooled flow boiling CHF is investigated in detail and the widely and precisely predictable correlations of the transient CHF correlations against outlet and inlet subcoolings in a short vertical tube are derived based on the experimental data at high liquid Reynolds number. The transient CHF correlations can describe the subcooled flow boiling CHFs for the wide range of flow velocities at high liquid Reynolds number obtained in this work within ±15% difference.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2010.05.035Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2010.05.035;
- PII
- S0029-5493(10)00361-4;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 240
- Journal Issue
- 10
- Journal Page Range
- p. 3145-3157
- ISSN
- 0029-5493
- CODEN
- NEDEAU
Conference
- Title
- 4. international topical meeting on high temperature reactor technology
- Acronym
- HTR 2008
- Dates
- 28 Sep - 1 Oct 2008
- Place
- Washington, DC (United States)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 42013333
- Subject category
- S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- BOILING; CRITICAL HEAT FLUX; EXPERIMENTAL DATA; FLOW RATE; HEAT TRANSFER; PUMPS; REYNOLDS NUMBER; ROUGHNESS; STAINLESS STEEL-304; STEADY-STATE CONDITIONS; SUBCOOLING; SURFACES; THICKNESS; TUBES; WALLS; WATER
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; COOLING; CORROSION RESISTANT ALLOYS; DATA; DIMENSIONLESS NUMBERS; DIMENSIONS; ENERGY TRANSFER; EQUIPMENT; HEAT FLUX; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; HYDROGEN COMPOUNDS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; NICKEL ALLOYS; NUMERICAL DATA; OXYGEN COMPOUNDS; PHASE TRANSFORMATIONS; STAINLESS STEELS; STEEL-CR19NI10; STEELS; SURFACE PROPERTIES; TRANSITION ELEMENT ALLOYS
Optional Information
- Copyright
- Copyright (c) 2010 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.