STUDY ON TRANSIENT HEAT TRANSFER OF FILM BOILING DUE TO ARRIVAL OF PRESSURE SHOCK

1982 ◽  
Author(s):  
Akira Inoue ◽  
Shigebumi Aoki ◽  
M. Aritomi ◽  
H. Kataoka ◽  
A. Matsunaga
Keyword(s):  
Heat Transfer ◽  
Transient Heat Transfer ◽  
Film Boiling ◽  
Pressure Shock

Destabilization of Film Boiling Due to Arrival of a Pressure Shock—Part I: Experimental

1981 ◽  
Vol 103 (3) ◽  
pp. 459-464 ◽  
Author(s):  
A. Inoue ◽  
S. G. Bankoff
Keyword(s):  
Heat Transfer ◽  
Horizontal Tube ◽  
Nucleate Boiling ◽  
Transient Heat Transfer ◽  
Film Boiling ◽  
Vapor Film ◽  
Pressure Shock ◽  
Transfer Rates ◽  
Vapor Explosions ◽  
Film Collapse

Transient heat transfer from an electrically-heated 3 mm o.d. horizontal tube, initially in subcooled film boiling, was measured immediately after passage of a shock wave of 1–5 × 105 N/m2 over-pressure. The fluids tested were Freon-113 and 95 percent ethanol-5 percent water at initially 0.5–2 × 105 N/m2 at 22–24° C. Transient heat transfer rates, averaged over 0.5–1 ms after vapor film collapse, ranged up to 20 times the steady-state value. The maximum transient flux occurred at supercritical contact temperatures, with frequently a minimum in the range of contact temperatures between the homogeneous nucleation and the critical temperature. Photography at 5000 frames/s showed apparently complete vapor film collapse within one or two frames, followed by re-establishment of film boiling in ∼1 ms, and eventually nucleate boiling in ∼100 ms. The surface temperature which gave the highest peak transient flux shifted appreciably with increasing shock pressure, which indicates some compressibility even after “contact” was made. Implications for vapor explosions are discussed.

scholarly journals Transient Heat Transfer in an Out-of-Pile SCWR Fuel Assembly Test at Near-Critical Pressure

2017 ◽  
Vol 4 (1) ◽  
Author(s):  
Thomas Schulenberg ◽  
Hongbo Li
Keyword(s):  
Heat Transfer ◽  
Heat Flux ◽  
Supercritical Water ◽  
Physical Models ◽  
Transient Heat Transfer ◽  
Film Boiling ◽  
Critical Conditions ◽  
Boiling Crisis ◽  
Look Up Table ◽  
System Pressure

While supercritical water is a perfect coolant with excellent heat transfer, a temporary decrease of the system pressure to subcritical conditions, either during intended transients or by accident, can easily cause a boiling crisis with significantly higher cladding temperatures of the fuel assemblies. These conditions have been tested in an out-of-pile experiment with a bundle of four heated rods in the supercritical water multipurpose loop (SWAMUP) facility coconstructed by CGNPC and SJTU in China. Some of the transient tests have been simulated at KIT with a one-dimensional (1D) matlab code, assuming quasi-steady-state flow conditions, but time dependent temperatures in the fuel rods. Heat transfer at supercritical and at near-critical conditions was modeled with a recent look-up table of Zahlan (2015, “Derivation of a Look-Up Table for Trans-Critical Heat Transfer in Water Cooled Tubes,” Ph.D. dissertation, University of Ottawa, Ottawa, ON, Canada.), and subcritical film boiling was modeled with the look-up table of Groeneveld et al. (2003, “A Look-Up Table for Fully Developed Film Boiling Heat Transfer,” Nucl. Eng. Des., 225(1), pp. 83–97.). Moreover, a conduction controlled rewetting process was included in the analyses, which is based on an analytical solution of Schulenberg and Raqué (2014, “Transient Heat Transfer During Depressurization From Supercritical Pressure,” Int. J. Heat Mass Transfer, 79(12), pp. 233–240.). The method could well reproduce the boiling crisis during depressurization from supercritical to subcritical pressure, including rewetting of the hot zone within some minutes, but the peak temperature was somewhat under-predicted. Tests with a lower heat flux, which did not cause such phenomena, could be predicted as well. In another test with increasing pressure, however, a boiling crisis was also observed at a heat flux, which was significantly lower than the critical heat flux (CHF) predicted by the CHF look-up table of Groeneveld et al. (2007, “The 2006 CHF Look-Up Table,” Nucl. Eng. Des., 237(15–17), pp. 1909–1922.). The paper is summarizing the physical models and the numerical approach. Comparison with experimental data is used to discuss the applicability of the method for the design of supercritical water-cooled reactors (SCWR).

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