Program to Develop Acoustic Emission--Flaw Relationship for Inservice Monitoring of Nuclear Pressure Vessels. Progress Report, October 1, 1977--January 1, 1978

摘要

This program is directed to providing an experimental evaluation of detecting and analyzing flaw growth in reactor pressure boundaries through continuous monitoring for acoustic emission (AE). The investigation is currently limited to A533B, Class 1 material. Program primary objectives are: develop criteria for distinguishing significant flaws from innocuous sources; develop an AE-flaw damage model to serve as a basis for relating inservice AE to pressure vessel integrity. This report covers program work period October 1, 1977 to January 1, 1978. A room temperature fracture test was performed on a one-inch thick by six-inch wide single-edge notch (SEN) specimen. The results were similar to AE-fracture test data obtained on 2T-CT laboratory specimens in that the majority of AE occurred during crack propagation. (ERA citation 03:052465)