Preliminary Stress Corrosion Cracking Modeling Study of a Dissimilar Material Weld of Alloy (Inconel) 182 with Stainless Steel 316 in Pressurized Water Nuclear Reactor
DOI:
https://doi.org/10.6000/1929-6002.2014.03.04.9Keywords:
Dissimilar Welds, Pressurized Water Stress Corrosion Cracking, Semi-Empiric-Probabilistic Modeling, Slow Strain Rate Tests, Weld Nickel Alloys (Inconel) 82/182Abstract
Dissimilar welds (DW) are normally used in many components junctions in structural project of PWR (Pressurized Water Reactors) in Nuclear Plants. One had been departed of a DW of a nozzle located at a Reactor Pressure Vessel (RPV) of a PWR reactor, that joins the structural vessel material with an A316 stainless steel safe end. This weld is basically done with Inconel/Alloy 182 with a weld buttering of Inconel/Alloy 82. It had been prepared some axial cylindrical specimens retired from the Alloy 182/A316 weld end to be tested in the slow strain rate test machine located at CDTN laboratory. Based in these stress corrosion susceptibility results, it was done a preliminary semi-empiric modeling application to study the failure initiation time evolution of these specimens. The used model is composed by a deterministic part, and a probabilistic part according to the Weibull distribution. It had been constructed a specific Microsoft Excel worksheet to do the model application of input data. The obtained results had been discussed according with literature and also the model application limits.
References
Aly OF. Analysis and Preliminary Modeling of Alloy 182 Data– CDTN. (Análise e Modelagem Preliminar de Dados de liga 182 – CDTN). São Paulo: IPEN, February 2009; 12. plus attached files (Internal Report).
Schvartzman MMAM, Neves CFC, Matias A, Lourenço LI. Susceptibility Evaluation to Stress Corrosion Cracking of Inconel 600 MA in Nuclear Reactor Environment (Avaliação da susceptibilidade à corrosão sob tensão do Inconel 600 MA em ambiente de reator nuclear). In: Proceedings of Anual Congress of ABM-International, 60, 2005, Belo Horizonte.... Belo Horizonte: ABM -Associação Brasileira de Metalurgia, Materiais e Mineração 2005.
Staehle RW. Combining design and corrosion for predicting life. In: R.N. Parkins (Ed.), Life Prediction of Corrodible Structures, Vol. 1, NACE International, Houston 1994; pp. 138-291.
White GA, Nordmann NS, Hickling J, Harrington CD. Development of Crack Growth Rate Disposition Curves for Primary Water Stress Corrosion Cracking (PWSCC) of Alloy 82, 182, and 132 Weldments. In.: Proceedings of the 12th International Conference on Environmental Degradation of Materials in Nuclear Power System – Water Reactors – Edited by T.R. Allen, P.J. King, and L. Nelson TMS (The Minerals, Metals & Materials Society) 2005.
Scott P, Foucault M, Brugier B, Hickling J, McIlree A. Examination of Stress Corrosion Cracks in Alloy 182 Weld Metal After Exposure to PWR Primary Water. In.: Proceedings of the 12th International Conference on Environmental Degradation of Materials in Nuclear Power System – Water Reactors – Edited by T.R. Allen, P.J. King, and L. Nelson TMS (The Minerals, Metals & Materials Society) 2005; pp. 497-509.
IAEA. Assessment and management of ageing of major nuclear power plant components important to safety: Pressurized water reactor pressure vessels. Vienna: IAEA 1997.
Aly OF. Analysis and Preliminary Modeling of Alloy 182 Data Complement– CDTN. (Complemento da Análise e Modelagem Preliminar de Dados de liga 182 – CDTN). São Paulo: IPEN, March 2009; 5 p. (Internal Report).
Dorner WW. Using Microsoft Excel for Weibull Analysis. QCI International (USA), 1999; Access on August 2012: http://www.qualitydigest.com/jan99/html/body_weibull.html
Staehle RW. Bases for Predicting the Earliest Penetrations Due to SCC for Alloy 600 on the Secondary Side of PWR Steam Generators. Washington, DC: USNRC, 2001. (NUREG/CR-6737 ANL-01/20 RWS 151 Report), Access on August 2013: http://adamswebsearch2.nrc.gov/idmws/ doccontent.dll?library=PU_ADAMS^PBNTAD01&ID=004026229 or http://www.nrc.gov/reading-rm/doc-collections/nuregs/ pubs/ (input ADAMS number ML012610214 (September, 2001).
Pathania RS, Gelpi A, Foucault M, Stuckey K, Fyfitch S, Sarver JM. Stress Corrosion Cracking of Welding Alloy 600 Mockups. EPRI: Palo Alto, CA, 1997 (TR-104831).
White G, Gorman J, Nordmann N, Jones P, Kreider M, Hickling J. Materials Reliability Program Crack Growth Rates for Evaluating Primary Water Stress Corrosion Cracking (PWSCC) of Alloy 82, 182, and 132 Welds. (MRP-115-EPRI 1006696 Final Report) Dominion Engineering, Inc.: Reston, VA, November 2004, Access on August 2013: http://www.epriweb.com/public/000000000001006696.pdf
Downloads
Published
How to Cite
Issue
Section
License
Copyright (c) 2014 Journal of Technology Innovations in Renewable Energy
This work is licensed under a Creative Commons Attribution 4.0 International License.
Policy for Journals/Articles with Open Access
Authors who publish with this journal agree to the following terms:
- Authors retain copyright and grant the journal right of first publication with the work simultaneously licensed under a Creative Commons Attribution License that allows others to share the work with an acknowledgement of the work's authorship and initial publication in this journal.
- Authors are permitted and encouraged to post links to their work online (e.g., in institutional repositories or on their website) prior to and during the submission process, as it can lead to productive exchanges, as well as earlier and greater citation of published work
Policy for Journals / Manuscript with Paid Access
Authors who publish with this journal agree to the following terms:
- Publisher retain copyright .
- Authors are permitted and encouraged to post links to their work online (e.g., in institutional repositories or on their website) prior to and during the submission process, as it can lead to productive exchanges, as well as earlier and greater citation of published work .
