Latexman, thanks. I will review this. There is quite a lot of literature similar to this that investigate mass flows from pipe breaks connected to the pressure vessel of nuclear reactors. The problem is that they have high pressure and usually saturated liquid at inlet. The translation to my case is not so easy.
katmar, since I have very high velocities and high void it will be mist flow or in some cases perhaps annular mist. Likely some critical two phase model would be most useful. Since this is a exceptional disturbance case and existing installation I don't want to redesign unless absolutely necessary. A proper separation of steam and condensate for this case is not reasonable I think as flow is so much higher than at normal operation.
BigInch, the listed correlations are to my knowledge used for single phase pressure drop. With steam quality this low the homogeneous density will be 3-10 times that of the pure steam and the viscosity for calculating Reynold number needs some adapted equations. If you have used 1-phase pressure drop correlations for 2-phase with only compensation for density and viscosity I would be very interested. Do you have any reference for this. The installation investigated has a few drainage valves from preheaters via a flash tank to the condenser. The condensate will always flash heavily in the control valve so the flow to the flash tank will always be low quality steam. The flash tank has a steam pipe and a condensate pipe connected to the condenser. At this disturbance case the mass flow will be so high that proper separation is unlikely and the condensate U-tube will likely blow out and the 2-ph. steam will blow out both through steam and condensate pipe.