The Influence of Flooding Phenomenon to Pressure Drop on Hotleg Simulator with L/D=25

Marcellinus Sindhu


Cooling system in nuclear reactor is much influenced by counter-current flow. When a leakage is occured, coolant in primary circuit of hotleg and hot steam from reactor will flows in counter-current condition. An experimental investigation has been performed to examine the effect of flooding phenomenon on the pressure drop. It was observed using acrylic complex pipe as hotleg simulator consisting of three parts: horizontal, bend and inclined pipe. Geometrical sizes of pipes was in scale of 1/30 of the actual hotleg geometrical size in the PWR with inner diameter=25.4 mm, the horizontal pipe length L=635 mm, and inclined pipe length was 20 mm with an angle of 50o. Pressure drop was meassured by using differential pressure sensor installed in the lower-tank (RPV simulator) dan upper-tank (SG simulator). Pressure drop was observed before, during and after flooding. Based on the observation, it was found that the change of flow pattern is followed by the change of pressure drop. The results of this study were also compared with some correlations using the dimensionless superficial velocity parameter by Wallis correlation. Wallis correlation can be written as JG*1/2 + 0,3974 JL*1/2 = 0,4832 .

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Apip, Indarto, Deendarlianto, "Observasi karakteristik CCFL pada pipa kompleks", ReTII IX, 2014, hal 371-375.

Deendarlianto, Vallée, C., Lucas, D., Beyer, M., Pietruske, H., Carl, H., "Experimental Study on the Air/water Counter-current Flow Limitation in a Model of the Hot Leg of a Pressurized Water Reactor", Nuclear Engineering and Design, Vol. 238 (12), 3 hal 389-3402, 2008.

Hewitt, G.F., Lacey, P.M.C, Nicholls,B., "Transition in Film Flow in a vertical pipe", UKAEA Report AERE-R4022, Harwell, England, 1965.

Issa, S., Macian, R., "A review of CCFL phenomenon, Annals of Nuclear Energy", Elsevier, Vol. 38, pp. 1795-1819, 2011.

Issa, S., Macian, R., "Experimental investigation of countercurrent flow limitation (CCFL) in large-diameter hot-leg geometry : A detailed description of CCFL mechanism, flow pattern and high quality HSC imaging of the interfacial structure in a 1/3.9 scale of PWR geometry", Nuclear Engineering and Design, Elsevier, Vol. 280, pp. 550-563, 2014..

Kang, S.K., Chu, I.C., No, H.C., Chun, M.H., "Air–water countercurrent flow limitation in a horizontal pipe connected to an inclined riser", Journal of the Korean Nuclear Society, Vol. 31 (6), 548–560, 1999.

Navarro, M., "Study of countercurrent flow limitation in a horizontal pipe connected to an inclined one", Nuclear Engineering and Design Vol. 235, no. 10–12 , pp. 1139–1148, 2005.

Wallis, G.B., "One-dimensional Two-phase Flow", Mc Graw Hill, New York, pp. 336-345, 1969.

Wongwises, S., "Experimental Investigation of Two-Phase Countercurrent Flow Limitation in a Bend between Horizontal and Inclined Pipes", Experimental Thermal and Fluid Science, Volume 8, pp. 245-259, 1994.

Wongwises, S., "Flooding in a horizontal pipe with bend", Int.J.Multiphase Flow Vol 22, pp. 195-201, 1996.

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