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Stress Corrosion Cracking Behaviour Of Thermally Aged Alloy 182

Alloy 182 is an austenitic (FCC) nickel base Ni-Cr-Fe-Mn weld metal that is used as a weld filler or weld pad metal to join stainless steel reactor internals, reactor instrumentation penetrations and main coolant piping to the low-alloy steel reactor pressure vessel. Stress corrosion cracking (SCC) in alloy 182 dissimilar welds is one of the most important material degradation problems and an ongoing issue in boiling (BWR) and pressurized water reactors (PWR) world-wide with potential safety concerns.
Thermally activated preferential local ordering (unlike atom pairs is greater than that in a random solution) of elements within a lattice, over spatial dimensions that are typically on the order of a few nearest neighbor spacing 20 to 50 Å (2 to 5 nm) is referred as short range ordering (SRO). SRO causes lattice contraction and induces additional stress which is claimed as the driving force for SCC in the alloy 600, alloy 690, and alloy 182.

Product Number: ED22-17291-SG
Author: Siddharth Suman, Hans-Peter Seifert, Philippe Spätig, Stefan Ritter
Publication Date: 2022
$20.00
$20.00
$20.00

To understand the effects of long-term thermal ageing on stress corrosion cracking (SCC) of alloy 182 in nuclear power plants, thermal ageing of as-welded alloy 182 was performed at 400 °C for 800 h, 2400 h, and 5500 h. Stress corrosion cracking initiation as well as crack growth tests were conducted in hydrogenated high-temperature water. SCC initiation was not affected by thermal ageing, but the number of tests were too low to make statistically sound conclusions. The SCC crack growth rates were moderately lower in thermally aged samples. However, the differences in growth rates were diminishing with more aggressive testing conditions (higher temperature and KI). There is thus no evidence for adverse effects of thermal aging on SCC in Alloy 182 in long-term operation.

To understand the effects of long-term thermal ageing on stress corrosion cracking (SCC) of alloy 182 in nuclear power plants, thermal ageing of as-welded alloy 182 was performed at 400 °C for 800 h, 2400 h, and 5500 h. Stress corrosion cracking initiation as well as crack growth tests were conducted in hydrogenated high-temperature water. SCC initiation was not affected by thermal ageing, but the number of tests were too low to make statistically sound conclusions. The SCC crack growth rates were moderately lower in thermally aged samples. However, the differences in growth rates were diminishing with more aggressive testing conditions (higher temperature and KI). There is thus no evidence for adverse effects of thermal aging on SCC in Alloy 182 in long-term operation.