Corrosion behavior of neutron absorbing Ti-Gd alloys in simulated spent nuclear fuel pool water
Source abstract
Abstract
The purpose of this study is to investigate the corrosion behavior of Ti-Gd alloys that were fabricated as a neutron absorbing material for storage of spent nuclear fuel in a boric acid solution at 50 °C. The electrochemical corrosion current and weight loss of the alloys increased with increasing Gd content. Gd-rich particles distributed in the Ti matrix were preferentially dissolved in the solution by a micro-galvanic effect with the cathodic Ti matrix. Oxide films grown on the alloys revealed a lower charge transfer resistance, lower electrical resistance, and higher donor density compared to those of pure Ti.
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Research context
OpenAlex topics: Nuclear Materials and Properties · Hydrogen embrittlement and corrosion behaviors in metals · Fusion materials and technologies
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
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