Server maintenance is scheduled for Saturday, December 21st between 6am-10am CST.

During that time, parts of our website will be affected until maintenance is completed. Thank you for your patience.

Menu
Search
Filters
Close
Menu

Products tagged with 'alloy 600'

View as
Sort by
Display per page
Picture for Effect Of Applied Stress On The Selective Oxidation Of Ni-Base Alloys Exposed To PWR Primary Water And Rhines Pack Environments
Available for download

Effect of Applied Stress on the Selective Oxidation of Alloy 600 Exposed To PWR Primary Water and Rhines Pack Environments

Product Number: ED22-17328-SG
Author: Karen Kruska, Ziqing Zhai, Brian J Riley, Matthew J Olszta, Daniel K Schreiber
Publication Date: 2022
$20.00

Alloy 600 is known to be susceptible to intergranular attack (IGA) and stress corrosion cracking (SCC) under pressurized water reactor (PWR) primary water conditions, leading to the replacement of some steam generator components with the more SCC-resistant Alloy 690.3 Despite this shift many Alloy 600 components are still found in service today. A substantial body of research has identified many underlying processes leading to the degradation of Alloy 600.
Picture for Intergranular Oxidation Of Unstressed Alloy 600 SA And Alloy 600TT In PWR Primary Water
Available for download

Intergranular Oxidation Of Unstressed Alloy 600 SA And Alloy 600TT In PWR Primary Water

Product Number: ED22-17279-SG
Author: Daniel K. Schreiber, Karen Kruska, Matthew J. Olszta, Peter H. Chou
Publication Date: 2022
$20.00

Alloy 600 (Ni-16Cr-9Fe) is well known to exhibit intergranular corrosion and intergranular stress corrosion cracking (IGSCC) upon exposure to high temperature water environments, including those found in service environments of pressurized water reactors (PWR). While the higher Cr content alloy 690 exhibits superior IGSCC resistance in these environments, alloy 600 is still in use at many light water reactor plants. Part of the difficulty in assessing alloy 600 performance is the significant variability in behavior from heat to heat, both from the standpoint of initial alloy chemistry and the subsequent thermomechanical treatment of the material.
Picture for Microstructure Characterization of Alloy 600TT Steam Generator Tubing
Available for download

Microstructure Characterization Of Alloy 600TT Steam Generator Tubing

Product Number: ED22-17239-SG
Author: Amanda Jenks, Chuck Marks, Brent Capell
Publication Date: 2022
$20.00

This paper describes the evolution of production standards for Alloy 600 tubing, the historical performance of steam generator tubing, and the results of microstructural analyses of archive and pulled tubing samples from commercial PWRs to address these issues. Alloy 600 is a corrosion-resistant nickel-base alloy that is used in a variety of applications that require good resistance to general corrosion, high strength, and good formability. It has been used extensively for steam generator tubing in commercial nuclear power plants, and this experience led to the use of several different types of Alloy 600 material.
Picture for The Effect Of Strain On Surface Residual Stress In Alloy 600 Tensile Specimens
Available for download

The Effect Of Strain On Surface Residual Stress In Alloy 600 Tensile Specimens

Product Number: ED22-17258-SG
Author: Karyn Cooper, William Brayshaw, Mark Chatterton, Sonya Pemberton, Stuart Medway, Jennifer Borg
Publication Date: 2022
$20.00

Nickel based Alloy 600 is used within the nuclear industry in structural components due to its good mechanical properties and general corrosion resistance, however upon exposure to primary water environments at elevated temperatures it can be affected by Primary Water Stress Corrosion Cracking (PWSCC). Nickel Based Alloy (NBA) susceptibility to PWSCC is dependent on a number of factors that include material type, condition and microstructure, as well as fabrication method, and can be investigated by uniaxial initiation testing in a primary water environment, where specimens are held at constant load under an elevated temperature.
Picture for The SCC Initiation Behavior Of Alloy 600 And SS 316L In Simulated PWR Primary Water Environments With A Lower Dissolved Hydrogen
Available for download

The SCC Initiation Behavior Of Alloy 600 And SS 316L In Simulated PWR Primary Water Environments With A Low Dissolved Hydrogen

Product Number: ED22-18330-SG
Author: Hsiang-Ling Shih, Mei-Ya Wang, Tsung-Kuang Yeh, Liang-Hsuan Chen
Publication Date: 2022
$20.00

Alloy 600 and SS 316L are common materials used for structural components of pressurized water reactors (PWRs). However, as PWRs age, incidents of general corrosion and stress corrosion cracking (SCC) are more likely to be found in the structural components. One of the major material degradation problems is primary water stress corrosion cracking (PWSCC).
Categories
Industry
Popular tags
View all

Association for Materials Protection and Performance

© AMPP All Rights Reserved.
Membership Terms of Content Use
Contact Customer Support