Unique challenges of performing non-destructive examinations behind the reactor vessel’s lower internals thermal shield
M Goodman
Westinghouse Inspection Services, Madison, Pennsylvania, USA
Email: goodmama@westinghouse.com
To support operating pressurised water reactor (PWR) plant license renewals and ageing management programmes, the Materials Reliability Program for Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227) was created. Through a screening process, MRP-227 identified PWR internals components that were susceptible to age-related degradation effects. An examination hierarchy was then established for these components based on how susceptible they are to age-related degradation. A number of these components are located behind the lower internals’ thermal shield.
This paper will examine the challenges to successfully performing visual, ultrasonic and eddy current examinations behind the thermal shield; including limited working space, as-found surface conditions, and identification of weld location.
This paper will examine the challenges to successfully performing visual, ultrasonic and eddy current examinations behind the thermal shield; including limited working space, as-found surface conditions, and identification of weld location.
