Apparatus for promoting intermixing of heated coolant streams in nuclear reactor

An apparatus for promoting intermixing of heated fluid streams within a nuclear reactor vessel is implemented in such structural configuration and disposition as to be capable of not only promoting uniform temperature distribution of a heated fluid stream flowing into an outlet nozzle but also reducing flow resistance which the heated fluid encounters within a upper plenum of the reactor vessel. The apparatus is disposed within a upper plenum (40) defined within a nuclear reactor vessel (10) of a nuclear reactor above a core having a low temperature region (a) and a high temperature region (d) where a heated fluid flows at a low temperature and a high temperature, respectively. The upper plenum (40) is hydraulically communicated to outlet nozzles (12) installed at a side wall of the nuclear reactor vessel (10). The apparatus includes heated fluid guide members each having a predetermined short length and installed within the upper plenum (40) for guiding a heated fluid (b') flowing out from the low temperature region of the reactor core to the vicinity of the outlet nozzle (12).