Since　the　passive　safety　system　turns　out　to　be　a　desirable　method　to　achieve　simplification　and　increase　the　reliability　of　the　performance　of　essential　safety　functions,　passive　technology　has　been　generally　applied　to　the　design　of　advanced　nuclear　power　plant.　The　traditional　generation　II+　reactor　CPR1000　plant　is　proposed　to　be　improved　with　some　passive　systems　to　enhance　safety　performance.　There　are　two　series　of　passive　safety　systems　for　CPR1000　in　this　paper,　one　of　them　contains:　(1)　the　RMT　(reactor　makeup　tank);　(2)　the　A-ACC　(advanced　accumulators);　(3)　the　IRWST　(in-containment　refueling　water　storage　tank);　(4)　the　PDS　(passive　depressurization　system);　and　(5)　the　PRHRS　(passive　residual　heat　removal　system),　which　is　installed　on　the　reactor　coolant　system　(RCS)　loop;　the　other　contains:　(1)　the　RMT　(reactor　makeup　tank);　(2)　the　A-ACC　(advanced　accumulators);　(3)　the　IRWST　(in-containment　refueling　water　storage　tank);　(4)　the　PDS　(passive　depressurization　system);　(5)　the　PEFS　(passive　emergency　feed　water　system),　which　is　installed　on　the　secondary　side　of　SGs.　In　this　research,　the　transient　characteristics　of　SGTR　accident　with　the　two　different　passive　residual　heat　removal　systems　which　are　PRHRS　and　PEFS　is　investigated　using　the　best-estimate　transient　simulation　code　Relap5/MOD3.3.　The　calculation　results　show　that　both　of　PRHRS　and　PEFS　could　remove　the　decay　heat　from　the　primary　loop　efficiently　to　ensure　the　reactor　safety　and　reduce　the　radioactive　leakage　to　mitigate　the　accident　impact　during　the　SGTR　accident.　Due　to　the　significant　cooling　effect　of　PRHRS　and　PEFS,　the　water　level　of　broken　SG　would　not　be　overfilled　in　both　conditions,　which　is　different　with　the　SGTR　accident　of　traditional　CPR1000.　Compared　with　the　PEFS,　the　PRHRS　performed　better　in　cooling　efficiency,　long-term　cooling　performance,　reducing　radioactive　leakage　capacity　and　mitigating　accident　effect.　©　2016　Association　for　Computing　Machinery　Inc.　All　Rights　Reserved.