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Assessment of Eddy Current Testing for the Detection of Cracks in Cast Stainless Steel Reactor Piping Components (NUREG/CR-6929)On this page: Download complete documentThe following links on this page are to documents in Adobe Portable Document Format (PDF). See our Plugins, Viewers, and Other Tools page for more information. For successful viewing of PDF documents on our site please be sure to use the latest version of Adobe. Publication InformationManuscript Completed: November 2006 1Visiting Intern - U.S. Nuclear Regulatory Commission AbstractStudies conducted at the Pacific Northwest National Laboratory (PNNL) in Richland, Washington, have focused on assessing the effectiveness and reliability of novel approaches to nondestructive examination (NDE) for inspecting coarse-grained, cast stainless steel reactor components. The primary objective of this work is to provide information to the U.S. Nuclear Regulatory Commission (NRC) on the utility, effectiveness, and reliability of advanced NDE methods as related to the inservice inspection of primary piping components in pressurized water reactors. This report describes progress, recent developments, and results from the assessment of eddy current testing (ET) for detection of surface-breaking cracks in cast stainless steel (CSS) reactor piping components from the inside surface of the pipe wall. In assessing the ET inspection technique, PNNL used a range of specimens from four different sources:
Eddy current studies were conducted on the inner-diameter surface of piping using a Zetec MIZ-27SI eddy current instrument and a Zetec C Z0000857-1 plus-point spot probe with an operating frequency of 250 kHz. To reduce noise effects, a subset of the CSS specimens was degaussed, resulting in noticeable improvements. In this report, results from laboratory studies for assessing detection, localization, and length sizing effectiveness are provided, and issues and anticipated future work are discussed. |
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