Stress corrosion crack initiation testing with tapered specimens in high-temperature water – results of a collaborative research project-Reference-Cited by-同舟云学术

Stress corrosion crack initiation testing with tapered specimens in high-temperature water – results of a collaborative research project

Published:2020-09-08 Issue:2 Volume:56 Page:103-118
ISSN:1478-422X
Container-title:Corrosion Engineering, Science and Technology
language:en
Short-container-title:Corrosion Engineering, Science and Technology

Author:

Bosch Rik-Wouter¹^ORCID,Ritter Stefan²^ORCID,Herbst Matthias³,Kilian Renate³,Burke M. Grace⁴,Duff Jonathan⁴,Scenini Fabio⁴,Gu Yuchen⁵,Dinu Alice⁶,Ehrnstén Ulla⁷,Toivonen Aki⁷,Novotny Radek⁸,Martin Oliver⁸,Perosanz Francisco-Javier⁹,Legat Andraž¹⁰,Zajec Bojan¹⁰^ORCID

Affiliation:

1. SCK CEN, Mol, Belgium

2. Paul Scherrer Institute (PSI), Villigen, Switzerland

3. Framatome GmbH, Erlangen, Germany

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

5. College of Engineering, Swansea University, Swansea, UK

6. RATEN ICN, Pitești, Romania

7. VTT Technical Research Centre of Finland Ltd., Espoo, Finland

8. EC – Joint Research Centre (JRC), Petten, The Netherlands

9. CIEMAT, Madrid, Spain

10. Slovenian National Building and Civil Engineering Institute (ZAG), Ljubljana, Slovenia

Publisher

Informa UK Limited

Subject

General Materials Science,General Chemical Engineering,General Chemistry

Link

https://www.tandfonline.com/doi/pdf/10.1080/1478422X.2020.1815460

Reference46 articles.

1. Stress Corrosion Cracking Behavior of Alloys in Aggressive Nuclear Reactor Core Environments

2. General corrosion and stress corrosion cracking of Alloy 600 in light water reactor primary coolants

3. Stress Corrosion Cracking Behavior in the Transition Region of Alloy 182/Low-Alloy Reactor Pressure Vessel Steel Dissimilar Metal Weld Joints in Light Water Reactor Environments

4. Féron D, Staehle R. eds. Stress corrosion cracking of nickel based alloys in water-cooled nuclear reactors – The Coriou effect, EFC Publications No. 67, Woodhead Publishing, ISBN: 978-0-08-100049-6, 2016.

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