SBLOCA accident

Large water inventory Slow transient SBLOCA Mitigation of accident consequence... 

After the incident at the Three Mile Island nuclear plant in 1979, the nuclear industry as a whole around the world intensified experimental and analytical investigations into all aspects of namral-circulation thermal-hydraulics. The small-break loss of coolant accident (SBLOCA) natore of the incident revealed the critical importance of natural circulation to understanding the response of such systems under these conditions. The entire industry worked to ensure that understanding of all aspects SBLOCAs, for existing and future systems, was correct and complete. 

SBLOCA Small-Break Loss of Coolant Accident... 

Aksan, N., 2008. International standard problems and small break loss-of-coolant accident (SBLOCA). Science and Technology of Nuclear Installations, http //dx.doi.org/10.1155/ 2008/814572. Article ID 814572, 22 p. 

The first experiment series included five SBLOCA tests with break in one hot leg of PACTEL. Three break sizes were used. Three tests included secondary system depressurization as an accident management measure. In all tests, only PSIS provided ECC water to the core. The primary pressure used in the tests was lower than the nominal operation pressure of PACTEL. Maximum operation pressure of the passive accumulators determined the upper limit of the experiment pressure (3.8 MPa). 

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