Hydrogen pick-up in zirconium alloys

Zirconium alloys are used as fuel cladding materials in light water nuclear reactors. During service at high temperature and pressure oxidation in water takes place, and part of the released hydrogen finds its way to the metal, potentially embrittling the material. The project aims at understanding the mechanisms involved in hydrogen transport in primarily Zircaloy-2 (a Zr-Sn-Fe-Cr-Ni-O alloy) used in boiling water reactors. The oxide-metal interface region of both autoclave tested and irradiated material is studied by atom probe tomography (APT), and hydrogen transport and reduction is modeled using ab-initio methods (DFT). The function of transition metal atoms as sites for hydrogen reduction is studied.​​

Participants

Hans-Olof Andrén (contact)

Professor at Applied Physics, Materials Microstructure

Mikaela Lindgren

Doktorand at Chemical and Biological Engineering, Environmental Inorganic Chemistry

Itai Panas

Professor at Chemical and Biological Engineering, Environmental Inorganic Chemistry

Gustav Sundell

Doktor at Applied Physics, Materials Microstructure

Mattias Thuvander

Docent at Applied Physics, Materials Microstructure

Collaborations

Imperial College London

London, United Kingdom

Pennsylvania State University

State college, USA

Sandvik Materials Technology

Sandviken, Sweden

University of Manchester

Manchester, United Kingdom

University of Oxford

Oxford, United Kingdom

Vattenfall

Stockholm, Sweden

Funding

Westinghouse Electric Sweden AB

Funding years 2011–2015

More information

Created

2015-02-19