Technical Letter Report, An Evaluation of Ultrasonic Phased Array Testing for Reactor Piping System Components Containing Dissimilar Metal Welds, JCN N6398, Task 2A

Diaz, Aaron A. ; Cinson, Anthony D. ; Crawford, Susan L. ; Anderson, Michael T.

关键词: ALLOYS;    CARBON;    CONFIGURATION;    COOLANTS;    NOZZLES;    NUCLEAR POWER PLANTS;    PRESSURIZERS;    PWR TYPE REACTORS;    REACTOR COMPONENTS;    REACTOR VESSELS;    RELIABILITY;    SHUTDOWN;    STAINLESS STEELS;    STEAM;    STEELS;    STRESS CORROSION;    SURGES;    TESTING;    ULTRASONIC TESTING;    ULTRASONIC WAVES;   

DOI  :  10.2172/969173
RP-ID  :  PNNL-19018
PID  :  OSTI ID: 969173
Others  :  Other: 401001060
Others  :  TRN: US1000257

美国|英语

来源: SciTech Connect

【 摘 要 】

Research is being conducted for the U.S. Nuclear Regulatory Commission at the Pacific Northwest National Laboratory to assess the effectiveness and reliability of advanced nondestructive examination (NDE) methods for the inspection of light-water reactor components. The scope of this research encomÂŹpasses primary system pressure boundary materials including dissimilar metal welds (DMWs), cast austenitic stainless steels (CASS), piping with corrosion-resistant cladding, weld overlays, inlays and onlays, and far-side examinations of austenitic piping welds. A primary objective of this work is to evaluate various NDE methods to assess their ability to detect, localize, and size cracks in steel components that challenge standard and/or conventional inspection methodologies. This interim technical letter report provides a summary of a technical evaluation aimed at assessing the capabilities of phased-array (PA) ultrasonic testing (UT) methods as applied to the inspection of small-bore DMW components that exist in the reactor coolant systems (RCS) of pressurized water reactors (PWRs). Operating experience and events such as the circumferential cracking in the reactor vessel nozzle-to-RCS hot leg pipe at V.C. Summer nuclear power station, identified in 2000, show that in PWRs where primary coolant water (or steam) are present under normal operation, Alloy 82/182 materials are susceptible to pressurized water stress corrosion cracking. The extent and number of occurrences of DMW cracking in nuclear power plants (domestically and internationally) indicate the necessity for reliable and effective inspection techniques. The work described herein was performed to provide insights for evaluating the utility of advanced NDE approaches for the inspection of DMW components such as a pressurizer surge nozzle DMW, a shutdown cooling pipe DMW, and a ferritic (low-alloy carbon steel)-to-CASS pipe DMW configuration.