Chromium enrichment on the habit plane of dislocation loops in ion-irradiated high-purity Fe–Cr alloys

Author:

Bhattacharya A.,Meslin E.,Henry J.,Pareige C.,Décamps B.,Genevois C.,Brimbal D.,Barbu A.

Funder

French Network EMIR

EFDA (European Fusion Development Agreement)

University of Rouen

Publisher

Elsevier BV

Subject

Metals and Alloys,Polymers and Plastics,Ceramics and Composites,Electronic, Optical and Magnetic Materials

Reference47 articles.

1. High-chromium ferritic and martensitic steels for nuclear applications;Klueh,2001

2. Current status and future R&D for reduced-activation ferritic/martensitic steels

3. Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure

4. Klueh RL. In: Proceedings of the Symposium on materials for spallation neutron sources. The Minerals, Metals, & Materials Society; 1997. p. 67.

5. Irradiation embrittlement of neutron-irradiated low activation ferritic steels

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