Interest　in　evaluation　of　reactor　response　and　off-site　consequences　following　beyond　design　basis　accidents　has　significantly　increased　after　Fukushima.　MELCOR　is　an　advanced　computational　aid　that　has　been　widely　used　and　adapted　to　various　reactor　designs　for　severe　core　damage　analyses.　This　paper　summarizes　the　core　thermal　hydraulic　response　for　a　hypothetical　severe　accident　caused　by　station　blackout　with　failure　of　the　steam　generator　safety　relief　valve　at　a　Chinese　pressurized　reactor　1000-MW　power　plant　-　CPR1000　using　MELCOR.　Analytical　results　for　a)　temperature　distribution　of　the　fuel　pellets,　b)　the　fuel　cladding,　c)　flow　rate　of　the　coolant,　and,　d)　hydrogen　mass　changing　over　time　are　presented.　The　analyses　are　focused　on　safety　assessment　of　the　reactor　core　for　severe　accidents　and　are　part　of　the　overall　evaluation　of　safety　features　of　the　CPR1000　reactor　for　residual　risk　posed　by　severe　accidents.　(C)　2014　Elsevier　Ltd.　All　rights　reserved.