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Nuclear Materials

Design and Results of the Irradiation Corrosion Experiment (ICE)

3:00 PM–3:20 PM Feb 24, 2020 (US - Pacific)

San Diego Convention Ctr - Theater A-7

Description

Franziska Schmidt1, Yongqiang Wang2, Peter Hosemann1; 1University of California, Berkeley, 2Los Alamos National Laboratory

The coupled effects of simultaneous irradiation and corrosion on metals are still poorly understood at the atomic scale, in particular for molten salts or liquid metals. This leads to considerable difficulties in the design of reliable materials for use in advanced reactors. Our work presents the design and improvement of the already existing irradiation corrosion experiment (ICE) and first experimental results. Detailed data on the previously irradiated ICE II (lead-bismuth eutectic) sample is presented in addition to initial data and design changes on ICE III, which is designed to study the interaction between molten salt corrosion and displacement. TEM and high resolution cross section work has been completed on ICE II and first experiments on ICE III with LiCl-KCl and a pure Fe sample indicate a strong affinity for ferrous metals, which varies with Ni content, and the production of a stable oxide film.
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