Investigation of surface treatment effects on the environmentally-assisted cracking behaviour of Alloy 182 in boiling water reactor environment

Author:

Que Zaiqing1ORCID,Zajec Bojan2ORCID,Ritter Stefan3ORCID,Seppänen Tommi1,Saario Timo1ORCID,Toivonen Aki1,Treichel Aleksandra3,Lautaru Valentin4,Scenini Fabio5ORCID

Affiliation:

1. Nuclear Energy, VTT Technical Research Centre of Finland, Espoo, Finland

2. Lab for Metals, Corrosion and Anticorr. Protection, Slovenian National Building and Civil Engineering Institute (ZAG), Ljubljana, Slovenia

3. Lab for Nuclear Materials, Nuclear Energy and Safety Research Department, Paul Scherrer Institute (PSI), Villigen, Switzerland

4. Nuclear Materials, RATEN ICN, Pitesti, Romania

5. Department of Materials, University of Manchester, Materials Performance Centre, Manchester, UK

Funder

Horizon 2020

Swiss Federal Nuclear Safety Inspectorate

Publisher

Informa UK Limited

Subject

General Materials Science,General Chemical Engineering,General Chemistry

Reference35 articles.

1. Review of PWSCC and mitigation management strategies of Alloy 600 materials of PWRs

2. Effects of electropolishing on corrosion and stress corrosion cracking of Alloy 182 in high temperature water

3. Materials Reliability Program: GE Experience Report on Cracking in Alloy 182 (MRP-57): BWR Alloy 182 Stress Corrosion Cracking, EPRI Report, 2001.

4. Shoji T. Progress in the mechanistic understanding of BWR SCC and its implication to prediction of SCC growth behavior in plants, in 11th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Stevenson, Washington, USA, 2003.

5. Berger S, Kilian R, Ritter S, et al. Mitigation of crack initiation in LWRs (MICRIN+), in Eurocorr 2016 Conference, paper No. 65952., Montpellier, France, 2016.

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