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Picture for Effect Of Applied Stress On The Selective Oxidation Of Ni-Base Alloys Exposed To PWR Primary Water And Rhines Pack Environments
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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 Effect Of Dissolved Oxygen On The SCC Susceptibility And Oxidation Of Cold-Worked 316L SS In PWR Primary Water
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Effect Of Dissolved Oxygen On The SCC Susceptibility And Oxidation Of Cold-Worked 316L SS In PWR Primary Water

Product Number: ED22-17254-SG
Author: Thalita De Paula, Cécilie Duhamel, Catherine Guerre, Jérôme Crépin, Ian De Curières, Frédéric Datcharry, Marc Maisonneuve
Publication Date: 2022
$20.00

Austenitic stainless steels (SS), such as 304L and 316L alloys, are largely used for structural components in nuclear power plants due to their good corrosion resistance, especially under high temperatures and aqueous environments. However, operational experience on the primary circuit of pressurized water reactors (PWRs) has shown an increasing number of cases of stress corrosion cracking (SCC) on austenitic stainless steels components after long-term exposure.
Picture for Long-Term Aging Behavior Of Cold-Worked Alloy 690 In Simulated PWR Primary Water
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Long-Term Aging Behavior Of Cold-Worked Alloy 690 In Simulated PWR Primary Water

Product Number: ED22-18358-SG
Author: Ziqing Zhai, Matthew J. Olszta, Mychailo B. Toloczko
Publication Date: 2022
$20.00

Alloy 690 has been utilized since the late 1980s as a replacement for Alloy 600 in pressurized water reactors (PWR) pressure boundary components due to laboratory data indicating higher resistance to stress corrosion cracking (SCC). Although to date no SCC incidents have been reported on Alloy 690 components in service, the growing interest of extending the operation life of PWRs beyond 60 or even 80 years has raised concerns for the potential occurrence of long-range ordering (LRO) in Alloy 690 and its compatible weld metals.
Picture for Proposed Crack Growth Rate Disposition Curves For Stress Corrosion Cracking Of Alloy 82 In BWR Environments
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Proposed Crack Growth Rate Disposition Curves For Stress Corrosion Cracking Of Alloy 82 In BWR Environments

Product Number: ED22-18350-SG
Author: P.L. Andresen, D.J. Shim, T. Terachi, T. Yamada, Y. Nomura
Publication Date: 2022
$20.00

A database of SCC growth rates in commercial austenitic stainless steels exposed to pressurized water reactor (PWR) primary water environments was developed and analyzed from international data in high temperature water, with an emphasis on deaerated or hydrogenated water while also including water containing oxygen. Crack growth rate (CGR) disposition equations were derived to reflect the effects of stress intensity factor (K), temperature, Vickers hardness (HV, to represent retained deformation), with enhancement factors for oxygen-containing, high corrosion potential conditions. The tolerance to chloride and sulfate impurities in PWR primary water was also evaluated.
Picture for PWSCC Crack Growth Rate Testing Of Wrought And HIP Alloy 625 In A PWR Environment
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PWSCC Crack Growth Rate Testing Of Wrought And HIP Alloy 625 In A PWR Environment.

Product Number: ED22-18522-SG
Author: J. Borg, S. Medway, F. Pickering, C. Smith
Publication Date: 2022
$20.00

This paper will discuss the crack growth rates measured for four different heats of HIP material and discuss possible relationships with hardness and stress intensity factor, along with considerations of grain size and features observed on the fracture surface.
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