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Nanostructured Engineering Alloys for Nuclear Application

Published online by Cambridge University Press:  11 March 2011

Peter Hosemann ,
Erich Stergar ,
Andrew T. Nelson ,
C. Vieh  and
Stuart A. Maloy
Peter Hosemann
Affiliation:
Nuclear Engineering, University of California Berkeley, Berkeley, California;
Erich Stergar
Affiliation:
Nuclear Engineering, University of California Berkeley, Berkeley, California;
Andrew T. Nelson
Affiliation:
Material Science and Engineering, Los Alamos National Laboratory, Los Alamos, New Mexico.
C. Vieh
Affiliation:
Paul Scherrer Institute, Villigen, Switzerland
Stuart A. Maloy
Affiliation:
Material Science and Engineering, Los Alamos National Laboratory, Los Alamos, New Mexico.
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Abstract

In advanced nuclear applications, high temperature and a corrosive environment are present in addition to a high dose radiation field causing displacement damage in the material. In recent times it has been shown that Nanostructured Ferritic Alloys (NFA’s) such as advanced Oxide Dispersion Strengthened (ODS) steels are suitable for this environment as they tolerate high dose irradiation without significant changes in microstructure or relevant mechanical properties.

Ion beam irradiation is a fast and cost effective way to induce radiation damage in materials but has limited penetration depth. Therefore, small scale mechanical testing such as nanoindentation and micro compression testing in combination with FIB based sample preparation for micro structural characterization has to be performed allowing a full assessment of the materials’ behavior under radiation environment. In this work two different ODS materials have been irradiated using proton and combined proton and He beams up to 1 dpa at different temperatures. Nanoindentation and LEAP measurements were performed in order to assess the changes in properties of these alloys due to irradiation. The same techniques were applied to intermetallic nanostructured alloys in order to investigate the effectiveness of the metal-intermetallic interface to provide defect sinks for He and radiation damage. It was found that irradiation can cause the formation of intermetallic particles even at room temperature while increasing the material strength significantly.

Keywords

steelion-implantationnano-indentation
Type
Articles
Information
MRS Online Proceedings Library (OPL) , Volume 1298: Symposium Q/R/T – Advanced Materials for Applications in Extreme Environments , 2011 , mrsf10-1298-t01-09
Copyright
Copyright © Materials Research Society 2011

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