Flow instability research on steam generator with straight double-walled heat transfer tube for FBR; Pressure drop under high pressure condition

Liu, W.; Tamai, Hidesada; Yoshida, Hiroyuki  ; Takase, Kazuyuki; Hayafune, Hiroki; Futagami, Satoshi  ; Kisohara, Naoyuki 

To discuss the feasibility of Steam Generator (SG) with a straight double-walled heat transfer tube that used in the Fast Breeder Reactor (FBR) system, we need to construct thermal hydraulic design method that can predict the flow instability accurately. To verify and to improve the correlations that used in the thermal-hydraulic design of the SG, Japan Atomic Energy Agency has started experiments under high pressure conditions. Detailed thermal hydraulic data including pressure drop data have been derived. This research does the analysis to the performed experiments with using TRAC-BF1 code. The pressure drop under high pressure condition is verified. It is found that with using the drift flux model in Track code for the void fraction calculation, Pffan's correlation for the friction pressure drop calculation in single phase flow and Martinelli-Nelson two-phase multiplier, the pressure drop can be predicted conservatively.