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Experimental study on thermal stratification in a compact reactor vessel of advanced sodium cooled reactor; Influence of a column-type upper inner structure (UIS) under scram conditions

Kimura, Nobuyuki; Hayashi, Kenji; Tobita, Akira; Kamide, Hideki ; Miyake, Yasuhiro*

Thermal stratification after a scram is one of main thermal loads of a reactor vessel in sodium cooled fast reactor. Water experiments using an 1/10th scaled model were carried out for an advanced loop type sodium cooled reactor. The reactor vessel is highly compact and has an upper inner structure (UIS), which has a slit in radial direction for fuel handling. The jet from core outlet goes through the UIS slit and makes asymmetric and locally high velocity field in the reactor upper plenum. Steep temperature distribution across the stratification interface and temperature fluctuations were found near the UIS slit. It was revealed that they were resulted from the impingement of the jet through the slit at the interface. Parameter experiments showed the characteristics of thermal stratification interface.

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