Fatigue failure by In-line flow-induced vibration was reproduced under the similar condition of sodium leakage accident in Fast Breeder Reactor MONJU. 0.45% carbon steel test specimen was fixed in acrylic tube of the water flow loop equipment. A drilled small hole was introduced onto the surface of the test specimen. Variation of the natural frequency and strain amplitude was measured at every moment. Due to the corrosion fatigue, specimen failure was occurred by In-line flow-induced vibration. This phenomenon is significant in designing the nuclear power plant.