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Picture for Alloy 182 Models for the Prediction of the Susceptibility to SCC of BMI Nozzle J-welds
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Alloy 182 Models for the Prediction of the Susceptibility to SCC of BMI Nozzle J-welds

Product Number: ED22-17286-SG
Author: Thierry Couvant
Publication Date: 2022
$20.00

Stress Corrosion Cracking (SCC) models are important for engineering and regulatory assessments. The SCC time to the growth of a crack of engineering scale is the main fraction of component life prior to failure and is therefore of significant interest for modeling. However, the stochastic characteristics of early crack development is challenging for model development and validation.
Picture for Characterization Of Grain Boundary Cavity Evolution During Long-Term Crack Initiation Testing Of Cold Worked Alloy 690 In Simulated PWR Primary Water
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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.
Picture for Irradiation Accelerated Corrosion of 316L Stainless Steel T91 and Zircaloy-4 in Primary Water
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Irradiation Accelerated Corrosion of 316L Stainless Steel T91 and Zircaloy-4 in Primary Water

Product Number: 51317--9131-SG
ISBN: 9131 2017 CP
Author: Stephen Raiman
Publication Date: 2017
$20.00

Austenitic and ferritic-martensitic steel were irradiated with  protons while exposed to simulated PWR primary water for 4-72 hr in 320°C water with 3 wppm hydrogen while irradiated at surface dose rates from 400-4000 kGy/s (4x10-7 to 7x10-6 dpa/s).
Picture for Long-Term Crack Initiation Behavior Of Alloy 690 And Its Weld Metals In PWR Primary Water
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Long-Term Crack Initiation Behavior Of Alloy 690 And Its Weld Metals In PWR Primary Water

Product Number: 51321-17004-SG
Author: Ziqing Zhai; Mychailo Toloczko; Stephen Bruemmer
Publication Date: 2021
$20.00
Picture for Role of Material Condition on Precursor Corrosion Damage and Stress Corrosion Crack Initiation Behavior of Alloy 600 in PWR Primary Water
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Role of Material Condition on Precursor Corrosion Damage and Stress Corrosion Crack Initiation Behavior of Alloy 600 in PWR Primary Water

Product Number: 51320-14536-SG
Author: Ziqing Zhai, Mychailo Toloczko, Stephen Bruemmer
Publication Date: 2020
$20.00

Stress corrosion crack (SCC) initiation testing has been performed on a 15% cold-worked UNS N06600 (Alloy 600) heat in mill-annealed (MA), solution annealed (SA), and thermally treated (TT) conditions to assess the role of grain boundary (GB) carbides on stress-assisted intergranular attack (IGA) and short crack nucleation and growth. The SCC initiation tests were conducted at a constant load equivalent to the materials’ yield stress in 360oC simulated pressurized water reactor primary water. Results revealed the highest SCC initiation susceptibility occurred in the Alloy 600 MA material, followed by the TT and SA materials, suggesting that GB carbide distribution did not have a controlling effect on SCC initiation resistance. Quantitative assessments of IGA and short cracks were conducted to help understand this phenomenon, and the role of GB carbides in precursor damage development that leads to differences in macroscopic SCC initiation behavior are discussed. 
Picture for Some Effects Of Surface Finish And LWR Environment On Environmentally-Assisted Crack Initiation In Alloy 182
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Some Effects Of Surface Finish And LWR Environment On Environmentally-Assisted Crack Initiation In Alloy 182

Product Number: ED22-18329-SG
Author: M. Vankeerberghen, R.-W. Bosch, A. Dinu, M. Grimm, A. Hojná, P. J. Meadows, R. Novotny, F. Perosanz, Z. Que, S. Ritter, F. Scenini, A. Toivonen, L. Volpe, B. Zajec
Publication Date: 2022
$20.00

Environmentally-assisted cracking (EAC) of nickel-base alloys has been observed in the primary coolant of light water reactors (LWRs). One of the main issues is primary water stress corrosion cracking (PWSCC) of Alloy 182 which has been a concern for a long time. For assumed or existing defects, disposition curves (crack growth rate as function of stress intensity factor) are available.
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