Experimental study of the downstream effect of LOCA-generated debris on the pressure drop of full scale fuel assembly
The emergency core cooling system (ECCS) works to cool the reactor core in the event of a postulated loss-of-coolant accident (LOCA). The long-term reactor cooling water of ECCS comes from containment sump. Usually, the containment sump contains one or more screens to prevent the components of the ECCS from debris which could be washed into the sump. Large debris is blocked by the sump screens. However, some of the debris, such as fibrous, chemical precipitates and small particles may be ingested into the ECCS and subsequently into the reactor coolant systems (RCS), which would challenge the long-term core cooling (LTCC) and threaten the reactor core safety. NRC address this concern Generic Letter 2004-02. Westinghouse has evaluated the AP1000 1/4 height fuel assembly head-loss test in response to the issue. AVERA also perform the scaled 1/3 height mock-up fuel assembly test. The debris effect on the pressure drop of half-length mock-up PLUS7 fuel assembly of APR1400 were performed in KHNP. Numerical simulation by RELAP5-3D were performed for the debris-generated core blockage and full core as well as core bypass blockage condition were considered. However, the test in the works mentioned above use the scaled down FA (1/4, 1/3 or 1/2 length of a full FA), and didn't give the relationship between pressure drop and debris batches. The purpose of this study was to extend the debris effect to the full scale PWR fuel assembly, and identified batch by batch effect of debris to head loss of FA. The specific experimental procedure is concluded. The pressure drop test without adding debris is performed at the beginning and then three kinds of debris are added to the test loop step by step to test their effect on the pressure drop of fuel assembly. Two kinds of tests have been carried out, and the quantitative pressure data are obtained and analysis is provided. This work provides reliable and quantitative data for nuclear power plant (NPP) downstream effect analysis and safety analysis program, which is important to for licensing of NPP and further benchmark exercise. (authors)