The behavior of a homogeneous reactor core of the 300-MW(electric) class has been evaluated during the pretransition and transition phases of a hypothetical loss-of-flow accident without scram. The SIMMER-II code has been used to track core material redistribution processes, which can lead to recriticalities and secondary nuclear power excursions. One of the key questions of core disruptive accident analysis is if core meltdown inevitably leads to a bottled-up core situation with its energetics potential or if various phenomena exist (as material discharge of hot fuel through the axial blankets, drop-in of blanket material into the core region, etc.) that prevent the accident progression into a bottled-up transition phase pool. The analyses for the specified reactor design show that, taking into account the aforementioned phenomena, the dominant accident path will lead to the postaccident heat removal phase directly from the pretransition phase. The accident path into the transition phase with a bottled-up core situation and its energetics potential might thereby be avoided.