The research activities currently underway on the test transfer loops are the study of:

• the effect of heat flux on the frictional pressure drop under single and two phase flow conditions;
• the axial pressure and void fraction distributions in heated tubes oriented vertically or horizontally;
• the critical heat flux (CHF) in vertical and horizontal tubes.
• CHF in a test section having a geometry similar to a segment of nuclear fuel bundle;
• the effect of choking flow on CHF;
• the axial and angular temperature distributions on the surface of tested tubes oriented vertically or horizontally;
• the flow mixing mechanisms in interconnected subchannels with heat addition.