Study of the irradiation hardening of a Fe9Cr ferritic model alloy by nanoindentations

D. Zhou; P. Spätig; Q. Hayat; P. Song; N. Jennett; J.-C. Chen; P. Desgardin

Nuclear Materials and Energy (Jun 2024)

Study of the irradiation hardening of a Fe9Cr ferritic model alloy by nanoindentations

D. Zhou,
P. Spätig,
Q. Hayat,
P. Song,
N. Jennett,
J.-C. Chen,
P. Desgardin

Affiliations

D. Zhou: Paul Scherrer Institut (PSI), Nuclear Energy and Safety Research Department (NES), Laboratory for Nuclear Materials (LNM), CH-5232 Villigen PSI, Switzerland; Nuclear Power Institute of China, Chengdu 610213, China
P. Spätig: Paul Scherrer Institut (PSI), Nuclear Energy and Safety Research Department (NES), Laboratory for Nuclear Materials (LNM), CH-5232 Villigen PSI, Switzerland; Laboratoy for Reactor Physics and Systems Behaviour, École polytechnique fédérale de Lausanne(EPFL), CH-1015 Lausanne, Switzerland; Corresponding author at: Department of Nuclear Energy and Safety, Paul Scherrer Institute, 5232 Villigen, Switzerland.
Q. Hayat: Warwick Manufacturing Group, University of Warwick, Coventry, United Kingdom
P. Song: Paul Scherrer Institut (PSI), Nuclear Energy and Safety Research Department (NES), Laboratory for Nuclear Materials (LNM), CH-5232 Villigen PSI, Switzerland
N. Jennett: Strategic Measures Consultancy Ltd, United Kingdom
J.-C. Chen: Paul Scherrer Institut (PSI), Nuclear Energy and Safety Research Department (NES), Laboratory for Nuclear Materials (LNM), CH-5232 Villigen PSI, Switzerland
P. Desgardin: CEMHTI, CNRS, UPR3079, University of Orléans, F-45071 Orléans, France

Journal volume & issue: Vol. 39
p. 101667

Abstract

Read online

This paper presents a series of Berkovich indentation results obtained on unirradiated and 7.2 MeV proton irradiated specimens of a Fe9Cr model alloy with an equiaxed ferritic microstructure. Using a energy degrader wheel made of 24 aluminum foils of different thickness, a flat damage profile of about 50 μm resulted from the irradiation, allowing to perform indentations within a volume material that is homogeneously irradiated. The indentation size effect on measured hardness was analyzed with a model based on the disloction-slip distance theory built on the concept of combined spatial frequency of all obstacles to dislocation motion. The effects on hardness of the tip-specimen contact size (or penetration depth), dislocation density and mean distance between irradiation defects were quantified and discussed. The irradiation hardening was characterized by the increase of hardness determined at large penetration depths.

Published in Nuclear Materials and Energy

ISSN: 2352-1791 (Online)
Publisher: Elsevier
Country of publisher: United Kingdom
LCC subjects: Technology: Electrical engineering. Electronics. Nuclear engineering: Nuclear engineering. Atomic power
Website: http://www.journals.elsevier.com/nuclear-materials-and-energy/

About the journal

Abstract

Keywords