A test method for reliably and easily evaluating the condition of a reactor coolant pump (RCP) shaft when there is only limited access to the shaft at the coupling would enable the nuclear industry to evaluate these shafts > systems on-site. This project provides a testing a method which can be applied to identify the presence, Size, and location of shaft cracks in a vertical RCP shaft system. Confirmation of a theoretical analysis and development of the necessary "tools" will permit the definition of a test method which meets the project objectives while accounting for the boundary conditions particular to an RCP shaft system. It is anticipated that a procedure will result that may be used in any nuclear power plant to assess the RCP shaft system.
Anticipated Results:Application of Research Phase I will verify the theoretical analysis and demonstrate that the test procedure can be used to identify the presence of a vertical shaft crack. Phase II will refine the test method and account for the boundary conditions associated with an RCP shaft system. Phase II will result in test method which can easily be applied to any RCP shaft system.
