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2019 | OriginalPaper | Buchkapitel

Applicability of Alloy 690/52/152 Crack Growth Testing Conditions to Plant Components

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Abstract

A great deal of PWSCC testing has been conducted on a range of A690 materials. An expert panel organized by EPRI is working to collect all the available laboratory data for its applicability to actual plant components. This paper will review the considerations that are being used to perform this evaluation, and the results of that evaluation. One of the key variables is cold work, and detailed studies have been conducted to measure the residual strains, so as to determine the amount of cold work that can exist in a heat-affected-zone (HAZ) region of a typical weld. In addition to these measurements on weldments, limitations on bulk cold work on base metal imposed by all vendors will be reviewed. The effect of the orientation of the specimens tested will be compared with the orientations of typical flaws in operating plants, so as to determine the relevance of the data to those plants.

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Fußnoten
1
Strain is defined as the maximum local fiber elongation or contraction per unit length; and where more than one strain increment occurs (e.g., biaxiality or reversed bending), it shall be the sum of the absolute values of all the strain increments.
 
2
Strain resulting from final straightening operations performed on materials furnished in the solution annealed or heat treated condition need not be included in the computation of strain.
 
Literatur
1.
Zurück zum Zitat S.M. Bruemmer et al, Cold-work effects on stress corrosion crack growth in alloy 690 tubing and plate materials, in Proceedings, 17th Conference on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, August 2015 S.M. Bruemmer et al, Cold-work effects on stress corrosion crack growth in alloy 690 tubing and plate materials, in Proceedings, 17th Conference on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, August 2015
2.
Zurück zum Zitat ASME Boiler and Pressure Vessel Code, Section III, Rules for Construction of Nuclear Power Plants, ASME International, New York, NY ASME Boiler and Pressure Vessel Code, Section III, Rules for Construction of Nuclear Power Plants, ASME International, New York, NY
3.
Zurück zum Zitat T.M. Angeliu et al, Intergranular stress corrosion cracking of unsensitized stainless steels in BWR environments, in Proceedings, 9th Conference on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, August 1999 T.M. Angeliu et al, Intergranular stress corrosion cracking of unsensitized stainless steels in BWR environments, in Proceedings, 9th Conference on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, August 1999
4.
Zurück zum Zitat Alloy 690 procurement specification, Rev. 1, Electric Power Research Institute, Palo Alto, CA, report 1026723, 2012 Alloy 690 procurement specification, Rev. 1, Electric Power Research Institute, Palo Alto, CA, report 1026723, 2012
5.
Zurück zum Zitat P.L. Andresen, M.M. Morra, K. Ahluwalia, SCC of alloy 690 and its weld metals, Corrosion 2012, Paper C2012-0001187, NACE International, 2012 P.L. Andresen, M.M. Morra, K. Ahluwalia, SCC of alloy 690 and its weld metals, Corrosion 2012, Paper C2012-0001187, NACE International, 2012
6.
Zurück zum Zitat Martin M. Mora, M. Othon, Weld Slice DDC-52-LAS-2: 52 M Repair/52 M Weld Interfaces, Alloy 690/52/152 PWSCC Research Collaboration Meeting (Tampa, FL, 2016) Martin M. Mora, M. Othon, Weld Slice DDC-52-LAS-2: 52 M Repair/52 M Weld Interfaces, Alloy 690/52/152 PWSCC Research Collaboration Meeting (Tampa, FL, 2016)
Metadaten
Titel
Applicability of Alloy 690/52/152 Crack Growth Testing Conditions to Plant Components
verfasst von
Warren Bamford
Steve Fyfitch
Raj Pathania
Paul Crooker
Copyright-Jahr
2019
DOI
https://doi.org/10.1007/978-3-030-04639-2_2

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