DOI: 10.31399/asm.amp.2016-10.p016 ISSN:

Correlative Microscopy of Neutron-Irradiated Materials

Samuel A. Briggs, Kumar Sridharan, Kevin G. Field
  • Mechanical Engineering
  • Mechanics of Materials
  • General Materials Science

Abstract

Development of new, radiation-tolerant materials that maintain the structural integrity and safety margins over the course of a nuclear power reactor’s service life requires the ability to predict degradation phenomena. Modern post-irradiation examination methods make use of specialized high-flux test reactors and dedicated characterization facilities to limit occupational exposure and prevent the spread of radioactive contamination. This article illustrates the use of these advanced techniques to characterize precipitates in neutron-irradiated Fe-Cr-Al alloys.

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