Experimental studies into the processes accompanying an intercircuit steam generator break in the safe operating limits in HLMC reactor facilities

摘要

The paper presents the results of the processes accompanying an “intercircuit steam generator (SG) break” emergency in the safe operating limits in reactor facilities with lead and lead-bismuth coolants (HLMC). The flow rate of the water and the steam entering the coolant through the break corresponded to the bubble and, in part, to the flare outflow patterns with simulation of the steam generator operating conditions. Varied patterns were used to simulate the water and steam outflow via SG tube holes of various geometries, including through a side hole, into an ejector's neck and into the working clearance of a labyrinth screw pump, with simulation of different degrees of the light phase bubble dispersion in the coolant. The lead melt temperature was 400–550 °C, the pressure was 0.1 to 4.0 kgf 2 /cm, the water temperature at the test segment inlet was 20 °C, the water pressure was 0.2–8.0 kgf 2 /cm, the flow rate of the water injected into the liquid metal coolant was 0.5–200 kg/h, and the continuous steam load on the lead coolant free surface was up to 10.0. The geometry of the channels for the current of two-component flows (HLMC-water, steam) and that of the structural elements immersed in a two-component flow was varied.