Correlative Microscopy of Neutron-Irradiated Materials

• DOI: 10.31399/asm.amp.2016-10.p016
• Publication Date: 2023-08-28T04:58:01Z
• Authors: Samuel A. Briggs; Kumar Sridharan; Kevin G. Field
• Keywords: Characterization; Service life

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