The generic severe accident management guidelines (SAMG) were developed as a response to TMI-2 accident to improve the defense-in-depth (DiD) concept of light water reactors (LWRs). Various SAMGs were developed for plant specific application considering different objectives of severe accident management (SAM) and design features of nuclear reactors. To verify and validate the effectiveness of SAMG and SAM actions for mitigating accident consequences and terminating accident progression, the analytical simulation through best estimate codes were performed extensively to provide quantitative details for the assessment of an SAMG and its actions. The present study is carried out to review the representative works concerned with the assessment of SAMG actions in the pressurized water reactors (PWR) and European VVERs using analytical simulation. The outcomes would be valid to realize the improvement and development of assessment methodology in future studies.