Steam generator fabricated of alloy 600 tubes has been replaced in the last decades by newer versions built with alloy 690 or alloy 800 tubes. At first, it was thought that both alloys were resistant to SCC mechanisms but after several years of operation, some NPPs developed denting processes and IGSCC, especially in alloy 800. Corrosion products accumulated in the crevice area between tube-sheet and secondary tube surface of SG increase the stresses and produce a chemical more aggressive to the environment. These two points are the main factor to occur “denting” and increase the possibility of ODSCC can be developed. This chapter describes the failure analysis of an alloy 800 SG tube with only nine years of operation. Microstructural chara...
Incoloy-800 is a nickel-chromium alloy that is best known for its ability to maintain a stable struc...
Alloy 600, the material used for pressurized water reactor steam generator tubing, is susceptible to...
The main purpose of this project is to study and identify what elements that causes the corrosion of...
The ODSCC detected in the TSP position of Ulchin 3&4 SGs are typical ODSCC of Alloy 600MA tubes. The...
The ODSCC detected in the TSP position of Ulchin 3&4 SGs are typical ODSCC of Alloy 600MA tubes. The...
OAK-B135 An Investigation of the Mechanism of IGA/SCC of Alloy 600 in Corrosion Accelerating Heated ...
AbstractThis technical note provides some considerations for the metallographic observation of inter...
A pressurized water reactor (PWR) steam generator transfers heat from the primary water, heated in t...
This review considers the broad set of corrosive degradations that can occur in PWR steam generators...
Nickel-chromium-iron alloys, such as Alloy 600 and Alloy 690, are used in steam generator applicatio...
The degradation of steam generator tubes in pressurized water nuclear reactors continues to be a ser...
The safe and reliable operation of pressurized water reactors (PWRs) depends on the integrity of str...
It was discovered in a Korean PWR that an extensive number of very short and shallow cracks in the S...
Includes bibliographical references (leaves 115-124).The susceptibility of Steam Generator (SG) Tube...
Nuclear Steam Generator (SG) service reliability and longevity have been seriously affected worldwid...
Incoloy-800 is a nickel-chromium alloy that is best known for its ability to maintain a stable struc...
Alloy 600, the material used for pressurized water reactor steam generator tubing, is susceptible to...
The main purpose of this project is to study and identify what elements that causes the corrosion of...
The ODSCC detected in the TSP position of Ulchin 3&4 SGs are typical ODSCC of Alloy 600MA tubes. The...
The ODSCC detected in the TSP position of Ulchin 3&4 SGs are typical ODSCC of Alloy 600MA tubes. The...
OAK-B135 An Investigation of the Mechanism of IGA/SCC of Alloy 600 in Corrosion Accelerating Heated ...
AbstractThis technical note provides some considerations for the metallographic observation of inter...
A pressurized water reactor (PWR) steam generator transfers heat from the primary water, heated in t...
This review considers the broad set of corrosive degradations that can occur in PWR steam generators...
Nickel-chromium-iron alloys, such as Alloy 600 and Alloy 690, are used in steam generator applicatio...
The degradation of steam generator tubes in pressurized water nuclear reactors continues to be a ser...
The safe and reliable operation of pressurized water reactors (PWRs) depends on the integrity of str...
It was discovered in a Korean PWR that an extensive number of very short and shallow cracks in the S...
Includes bibliographical references (leaves 115-124).The susceptibility of Steam Generator (SG) Tube...
Nuclear Steam Generator (SG) service reliability and longevity have been seriously affected worldwid...
Incoloy-800 is a nickel-chromium alloy that is best known for its ability to maintain a stable struc...
Alloy 600, the material used for pressurized water reactor steam generator tubing, is susceptible to...
The main purpose of this project is to study and identify what elements that causes the corrosion of...