Abstract
In-Core Monitor (ICM) housing of BWR reactor pressure vessel is subjected to the flow induced vibration (FIV). The flow fluctuation takes places in the lower plenum of reactor pressure vessel. It is very much important to evaluate the structural integrity of ICM housing in order to maintain high operating rate. Thus we performed the FIV simulated fatigue test of ICM housing. However, the stress at the weld toe induced by FIV is sufficiently low not to fail. The fatigue endurance limit for the weld root fatigue test specimen with dull taper is 196 MPa. On the while, the fatigue endurance limit for the weld root fatigue test specimen with steep taper is not obtained. When the fatigue test results are approximated by the Stromeyer equation, the fatigue strength for the fatigue life of 109 cycles is estimated as 27 MPa. Finally we performed the fracture mechanics analysis, which indicates that the stress intensity factors for Mode I and II range from 0.1 to 0.2 MPam so that the fatigue crack is not initiated at the weld root by FIV.
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