The main objective of this paper is to sum up the experimental and theoretical work carried out by the authors and their groups over a period of several years, demonstrating and explaining three different types of two-phase flow oscillations, namely, density-wave type, pressure-drop type oscillations and thermal oscillations, encountered in various boiling flow channel systems.Classification of two-phase flow instabilities is summarized first. Three distinct types of two-phase flow oscillations and their mechanisms are explained. Since 1950's with the beginning of commercialization of nuclear reactors, the interest in two-phase flow instability studies started to grow in the western countries followed by the Soviet Union and China. Hence, in the literature review, the most available work to our knowledge is cited. The results of our experimental work on transient and sustained instabilities in single, double channel, cross-connected double channel, four parallel channel and four cross-connected parallel channel upf10w systems are presented. The effects of heat flux variations, inlet subcoo1ing, flow rate, inlet and exit restrictions are indicated. The effect of heat transfer augmentation on two-phase flow instabilities in a vertical single channel is also included. Numerical models which are based on the assumption of homogeneous two-phase flow and thermodynamic equilibrium of the two phases to predict both the steady state and transient behavior of forced convection boiling upf10w two-phase flow in a single channel are summarized and some of the results of these solutions are presented. Two different two-phase flow models, namely a constantproperty homogeneous flow model and a variable property-flux model which are used for the prediction of the pressure-drop and densitywave instability thresholds in a single boiling channel upflow system are mentioned and some of the solution results are presented.