Credit: 4 PDH
Course Fee: $36.00
The degradation of steam generator tubes in pressurized water nuclear reactors, particularly by stress corrosion cracking mechanisms, continues to be a serious problem. Primary water stress corrosion cracking is commonly observed at the roll transition zone at U-bends, at tube denting locations, and occasionally in plugs and sleeves. Outer-diameter stress corrosion cracking and inter granular attack commonly occur near the tube support plate crevice, near the tube sheet in crevices or under sludge piles, and occasionally in the free span. A particularly troubling recent trend has been the increasing occurrence of circumferential cracking at the RTZ on both the primary and secondary sides.
This course summarizes on the principal-corrosion-related degradation processes observed in steam generator tubing and provides the basis for the philosophy behind the new steam generator rule and Regulatory Guide.
Review the quiz before studying the course.
Course Author: USNRC
This course comes with a multiple-choice quiz. You can view the quiz and take the quiz if you are logged in your account. You can take the quiz for this online PDH course as many times until passed. The passing grade is 70% and above. After you pass the quiz simply follow the page, to pay for the course and print your certificate instantly. A copy of the certificate and receipt for this course will always be in your account.
This online PDH or CE course can also be used as a continuing education course for the following.