Published 2011 | Version v1
Miscellaneous

Heat transfer and critical heat flux of subcooled water flow boiling in a short horizontal tube

  • 1. Kyoto Univ., Inst. of Adv. Energy, Gokasho, Uji, Kyoto (Japan)
  • 2. Kyoto Univ., Dept. of Energy Science and Tech., Sakyo-ku, Kyoto (Japan)
  • 3. National Inst. for Fusion Science, Oroshi-cho, Toki, Gifu (Japan)

Description

The steady-state turbulent heat transfer (THT) due to exponentially increasing heat inputs with various exponential periods (Q=Q0exp(t/τ), τ=6.55 to 21.81 s) were systematically measured with the flow velocities, u, of 4.15, 7.05, 10.07 and 13.50 m/s by an experimental water loop flow. Measurements were made on a 6 mm inner diameter, a 59.2 mm effective length and a 0.4 mm thickness of HORIZONTAL Platinum (Pt) circular test tube. The relation between the steady-state turbulent heat transfer and the flow velocity were clarified. The steady state nucleate boiling heat transfer (NBHT) and the steady state critical heat fluxes (CHFs) of the subcooled water flow boiling for HORIZONTAL SUS304 circular test tube were systematically measured with the flow velocities (u=3.94 to 13.86 m/s), the inlet subcoolings (ΔTsub,in=81.30 to 147.94 K), the inlet pressures (Pin=786.29 to 960.93 kPa) and the increasing heat input (Q0 exp(t/τ), τ=8.36 s). The HORIZONTAL SUS304 test tube of inner diameter (d=6 mm), heated length (L=59.4 mm), effective length (Leff=48.4 mm), L/d (=9.9), Leff/d (=8.06) and wall thickness (δ=0.5 mm) with surface roughness (Ra=3.89 μm) was used in this work. The NBHT and the steady state CHFs of the subcooled water flow boiling for the HORIZONTAL SUS304 test tube were clarified at the flow velocities u ranging from 3.94 to 13.86 m/s. The steady-state THT data, the NBHT ones and the steady state CHF ones were compared with the values calculated by authors' THT correlation, their NBHT ones and their transient CHF ones against outlet and inlet subcoolings based on the experimental data for the VERTICAL circular test tubes with the flow velocities u ranging from 4.0 to 42.4 m/s. The influences of test tube orientation on the THT, the NBHT and the subcooled flow boiling CHF are investigated into details and the widely and precisely predictable correlations of the THT, the NBHT and the transient CHFs against outlet and inlet subcoolings in a short HORIZONTAL circular test tube are derived based on the experimental data. The THT correlation, the NBHT ones and the transient CHF ones for the HORIZONTAL test tube can describe the THT data, the NBHT ones and the subcooled flow boiling CHF ones for the wide ranges of ΔTsub,in, u and τ obtained in this work within ±15 % difference. (author)

Part of:
The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-14)

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
978-1-926773-05-6
Imprint Title
The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-14)
Imprint Pagination
766 Megabytes
Journal Page Range
[23 p.]

Conference

Title
14. International Topical Meeting on Nuclear Reactor Thermalhydraulics
Acronym
NURETH-14
Dates
25-30 Sep 2011
Place
Toronto, Ontario (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
47071038
Subject category
S42: ENGINEERING;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CRITICAL HEAT FLUX; FLOW RATE; HEAT TRANSFER; NUCLEATE BOILING; PIPES; STEADY-STATE CONDITIONS; TURBULENT FLOW
Descriptors DEC
BOILING; ENERGY TRANSFER; FLUID FLOW; HEAT FLUX; PHASE TRANSFORMATIONS; TUBES

Optional Information

Notes
Paper NURETH14-098, 49 refs., 1 tab., 16 figs.