AMPP Store - Products tagged with 'alloy 690'

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Characterization Of Grain Boundary Cavity Evolution During Long-Term Crack Initiation Testing Of Cold Worked Alloy 690 In Simulated PWR Primary Water

Product Number: ED22-17324-SG

Author: Ziqing Zhai, Mychailo Toloczko, Stephen Bruemmer

Publication Date: 2022

$20.00

Determining the resistance of high-Cr Ni-base Alloy 690 to environmental degradation during long-term pressurized water reactor (PWR) exposure is needed to confirm its viability as the replacement material for Alloy 600 and help establish a quantitative factor of improvement for stress corrosion crack (SCC) initiation. SCC initiation testing on cold-worked (CW) Alloy 600 materials in PWR primary water has demonstrated that intergranular (IG) attack is the precursor to SCC initiation in this material. In comparison, an equivalent degradation and cracking process does not exist in CW Alloy 690.

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Effect Of Thermal Aging On The Microstructure And Mechanical Properties Of High-Ni And Ni-Base Alloys

Product Number: ED22-17125-SG

Author: Caitlin Huotilainen, Zaiqing Que, Yanling Ge, Petteri Lappalainen, Noora Hytönen, Ritva Korhonen, Santtu Huotilainen

Publication Date: 2022

$20.00

High-strength materials with excellent corrosion resistance and mechanical properties are highly sought after for use in light water reactor (LWR) type nuclear power plants (NPP). In western pressurized water reactors (PWR), nickel-base alloys are often the main structural materials for the steam generator (SG) tubes, while in Russian PWRs or water-water energetic reactor (VVER) high-nickel alloys, for example XH35BT (35 wt.% Ni), can be found in some primary side high strength applications, such as reactor pressure vessel internals (RVI).

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Long Range Ordering In Thermally Treated And Cold-Worked Alloy 690

Product Number: ED22-17251-SG

Author: Daniel Brimbal, Pierre Joly, Claude Benhamou, Cécilie Duhamel, Michael A. Burke, Annie Pagès, Bénédicte Gueraud

Publication Date: 2022

$20.00

Nickel-chromium alloys may be susceptible to ordering under certain thermal aging conditions, resulting in the formation of an Ni2Cr phase. The Ni2Cr phase is a superlattice which can result in significant changes of the physical or mechanical properties compared to those of the disordered alloy. Alloy 690, which usually contains a bit less than two nickel atoms per chrom-ium atom, could potentially be susceptible to long-range ordering (LRO) or short-range ordering (SRO). SRO implies that a Cr atom has a high probability of having a Ni nearest neighbor and that small order domains containing at most a few atoms exist. LRO implies that small Ni2Cr clusters exist, and although they may not be visible by transmission electron microscopy (TEM) dark field imaging, they lead to the detection of
additional diffraction spots in selected area electron diffraction (SAED) patterns, contrary to SRO. Below the critical temperature for LRO, the formation of the long-range ordered structures is preceded by a period of short-range ordering.

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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.

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Long-Term Performance Of Alloy 690 In LWR Environment

Product Number: ED22-17284-SG

Author: Bogdan Alexandreanu, Yiren Chen, Xuan Zhang, Wei-Ying Chen

Publication Date: 2022

$20.00

Nickel-based Alloy 690 and the associated weld Alloys 52 and 152 are typically used for nozzle penetrations in replacement heads for pressurized water reactor (PWR) vessels, because of their increased resistance to stress corrosion cracking (SCC) relative to Alloys 600, 82, and 182. Many of these reactors are expected to operate for 40-80 years. Likewise, advanced water-cooled small modular reactors (SMRs) will use Ni-Cr alloys in their primary systems and are expected to receive initial operating licenses for 60 years.

Products tagged with 'alloy 690'

Characterization Of Grain Boundary Cavity Evolution During Long-Term Crack Initiation Testing Of Cold Worked Alloy 690 In Simulated PWR Primary Water

Effect Of Thermal Aging On The Microstructure And Mechanical Properties Of High-Ni And Ni-Base Alloys

Long Range Ordering In Thermally Treated And Cold-Worked Alloy 690

Long-Term Aging Behavior Of Cold-Worked Alloy 690 In Simulated PWR Primary Water

Long-Term Performance Of Alloy 690 In LWR Environment

Association for Materials Protection and Performance