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Picture for 05157 Critical Review: Fas Assessment Methods for
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05157 Critical Review: Fas Assessment Methods for Crack-Like Flaws in Pipelines

Product Number: 51300-05157-SG
ISBN: 05157 2005 CP
Author: Ming Gao, Richard McNealy, and Jose Loris, GE Energy; Ravi M. Krishnamurthy, Blade Energy Partners
Publication Date: 2005
$20.00

Currently, a number of fracture mechanics-based methods are available for crack assessment. In this paper, a critical review is given to failure assessment diagram (FAD), in particular the API 579-2000 fracture mechanics assessment method for crack-like flaws. Illustrations, arranged by applicability to field examples, demonstrate the approach.
Picture for 08150 A Case Study: ERW Seam Weld Failure
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08150 A Case Study: ERW Seam Weld Failure

Product Number: 51300-08150-SG
ISBN: 08150 2008 CP
Author: Ming Gao, Sergio Limon, David C. Katz, Ravi M. Krishnamurthy, and Rick Mcnealy
Publication Date: 2008
$20.00

A recent pre-1970 ERW Pipe Seam Weld Failure incident is presented. The investigation combines metallurgical and fractographic analysis, fracture mechanics testing, and failure analysis diagram to determine the origin and nature.
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 Effect of CP on the Occurrence of SCC in X80 and X100 Pipe Steels in a Near-Neutral pH Environment
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Effect of CP on the Occurrence of SCC in X80 and X100 Pipe Steels in a Near-Neutral pH Environment

Product Number: 51317--9147-SG
ISBN: 9147 2017 CP
Author: Li Yan
Publication Date: 2017
$20.00

In this work, stress corrosion cracking (SCC) of X80 and X100 pipe steels under various cathodic protection (CP) levels in near-neutral pH environment was investigated. The results showed that X100 tended to form longer SCC cracks compared to X80 steel.
intergranular, stress corrosion cracking, crack initiation, UNS N06690, cold work, creep cavities, grain boundary microstructure
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Precursor Evolution and SCC Initiation of Cold-Worked Alloy 690 in Simulated PWR Primary Water

Product Number: 51317--9475-SG
ISBN: 9475 2017 CP
Author: Ziqing Zhai
Publication Date: 2017
$20.00

Stress corrosion crack initiation of two thermally-treated, cold-worked UNS N06690 materials was investigated in 360 ºC simulated primary water using constant load tensile tests and blunt notch compact tension tests equipped with direct current potential drop for in-situ detection of cracking.
Picture for Mechanistic Understanding Of Irradiation Assisted Stress Corrosion Cracking
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Role of Grain Boundary Oxidation in Crack Initiation of Neutron-irradiated Stainless Steel

Product Number: ED22-17333-SG
Author: Srinivasan Swaminathan, Donghai Du, Gary S. Was
Publication Date: 2022
$20.00

Irradiation assisted stress corrosion cracking (IASCC) continues to be a major concern for the
structural integrity of core internals in both pressurized water reactors (PWRs) and boiling water
reactor (BWRs). While factors such as stress, an irradiated microstructure and a high temperature
water environment are required for IASCC, a better understanding of the underlying mechanism
has become a subject of intense long-term research. In the last two decades, much progress has
been made in understanding IASCC susceptibility, though a clear cause-and-effect has yet to be
established on the mechanism of intergranular cracking in highly neutron irradiated stainless steels
in the PWR environment.
Picture for SCC Initiation And Growth In PWR Primary Water Containing KOH Vs. Lioh
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SCC Initiation and Growth Rate Response of A-286 in B/Li and B/K Solutions 340°C

Product Number: ED22-17262-SG
Author: P.L. Andresen, P. Chou
Publication Date: 2022
$20.00

Stress corrosion cracking (SCC) initiation and growth rate testing was performed using Alloy A-286, a high-strength iron-base alloy, to evaluate for possible differences in response in boric acid solutions containing KOH vs. LiOH. PWRs are considering a switch from LiOH to KOH because of the uncertain future availability and high cost of Li. To achieve the same pH at temperature (pHT) in typical PWR primary water, the same molar concentration of Li and K is needed. The atomic weight of K is 39.1, which is 5.63 higher than the atomic weight of Li at 6.94, so 1 ppm Li yields the same pHT as 5.63 ppm K. The conductivity differs somewhat because of difference in the mobility of Li+ and K+.
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