The　two-phase　pressure　drop　characteristics　of　liquid　sodium　are　very　significant　for　the　safety　and　serious　incident　program　development　analysis　of　sodium-cooled　fast　reactor　(SFR).　In　this　paper,　the　boiling　two-phase　pressure　drop　experiments　of　liquid　sodium　were　conducted　in　a　7-rod　bundle　with　the　mass　flux　range　of　80　-390　kg/(m2.s),　heat　flux　up　to　120　kW/m2　and　the　absolute　pressure　range　of　7.5　-100　kPa.　The　experimental　results　show　that　the　frictional　multiplier　of　boiling　two-phase　liquid　sodium　in　the　rod　bundle　channel　decreases　with　the　increase　ofXLM.　Some　existing　two-phase　pressure　drop　correlations　in　the　literatures　were　assessed　and　compared　with　the　experimental　data　obtained　in　the　present　study.　Results　showed　that　these　correlations　could　not　predict　the　current　experiments　well　because　of　the　different　geometries　and　measurements　of　high　tem-perature　environment.　The　new　correlation　for　the　two-phase　friction　multiplier　of　liquid　sodium　was　developed　in　the　7　rod　bundle.　The　predicted　value　of　the　new　correlation　was　within　30　%　of　the　experimental　data　in　the　rod　bundle,　which　sufficiently　demonstrates　that　the　new　correlation　developed　in　this　paper　can　well　predict　the　boiling　two-phase　frictional　pressure　drop　of　liquid　sodium　in　the　rod　bundle.