[en] The analysis of transient two-phase flow phenomena is of much interest in the design and licensing of nuclear power reactors. Recently considerable progress in understanding and predicting transient two phase phenomena has been made by a combination of rigorous model development, advanced computational techniques and a number of small and large scale supporting experiments. However, it has been recognized that the greatest difficulty is associated with the development of the constitutive relations. MINCS-PIPE has been developed as a onedimensional analytic tool based on various two phase flow models from the one velocity and one temperature (1V1T) model to the two velocity and two temperature (2V2T) model to assess constitutive relations and to aid development of various experimental correlations. A description of the MINCS-PIPE as well as a developmental plan of MINCS are given in this report. (author)