Huaidong Chen

Investigation of eddy current examination on OD fatigue crack for steam generator tubes

The opening width of fatigue crack was very small, and conventional Bobbin probe was very difficult to detect it in steam generator tubes. Different sizes of 8 fatigue cracks were inspected using bobbin probe rotating probe. The analysis results showed that, bobbin probe was not sensitive for fatigue crack even for small through wall crack mixed with denting signal. On the other hand, the rotating probe was easily to detect all cracks. Finally, the OD phase to depth curve for fatigue crack using rotating probe was established and the results agreed very well with the true crack size.

Motion simulation of robot for nuclear reactor pressure vessel non-destructive detection based on SoftMotion

Reactor pressure vessels, as the most important security barrier for nuclear power plant safety, are the only part of nuclear power plant that cannot be replaced during the whole life. The security of the vessels is very important for the safety of nuclear power. The nuclear reactor pressure vessels NDT robots are very important equipments. The detection process for these pressure vessels using the robots requires absolute safety, so it is necessary to simulate the nuclear reactor pressure vessel NDT robot and verify the feasibility. In this paper, physical modeling, the D-H rule modeling, kinematics modeling and simulation for the nuclear reactor pressure vessel NDT robots are implemented and verified with joint simulation and MATLAB.