The　CHF　in　PWR　fuel　assemblies　is　usually　predicted　by　the　local　flow　correlation　approach　based　on　subchannel　analysis　while　the　effects　of　spacer　grids,　cold　walls,　non-uniform　heat　flux,　etc　are　investigated.　By　using　the　subchannel　code　ATHAS　to　calculate　each　set　of　bundle　CHF　data,　the　local　thermal-hydraulic　parameters　at　DNB　occurrence　point　were　obtained.　In　present　study,　the　minimum　DNBR　point　method　was　applied　to　develop　a　new　CHF　correlation　for　PWR　fuel　assemblies.　The　so-called　＂three-step　method＂　and　＂magnitude　analysis　method＂　were　used　to　determine　the　shape　and　the　expression　of　each　item,　respectively　and　the　least　square　method　was　applied　to　determine　the　coefficients　of　the　correlation.　Based　on　the　large　database　of　CHF　tests,　the　CHF　correlation　named　ACC　correlation　has　been　developed　to　calculate　the　risk　of　DNB.　The　analysis　and　assessment　results　indicate　that　the　ACC　correlation　can　fit　the　experimental　data　well　with　high　prediction　accuracy　and　correct　parametric　trends.　Coupled　with　subchannel　code　ATHAS,　this　correlation　can　simulate　the　thermal-hydraulics　performances　of　PWR　fuel　assemblies　exactly.