| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Materials Corrosion Behavior in Advanced Nuclear Reactor Environments II
|
| Presentation Title |
In-Situ Characterization of Heavy Liquid Metal Eutectic During Corrosion Using Laser Ablation Inductively Coupled Plasma Mass Spectrometry (LA-ICPMS) |
| Author(s) |
Nicole Virgili |
| On-Site Speaker (Planned) |
Nicole Virgili |
| Abstract Scope |
The design of the Breeding Blanket in Tokamak fusion energy systems has to guarantee sufficient operation availability in addition to its functions, that are, tritium breeding self-sufficiency, power extraction and shielding, under extremely harsh operating conditions in terms of heat flux and neutron dose as well as chemical environment of the coolant and breeder that challenge structural materials.
Regarding corrosion in Water Cooled Lithium Lead Breeding Blanket, it is crucial to quantify the solubility of corrosion products in the liquid metal.
This experiment conducted at UC Berkeley laboratory aims to outline a systematic approach to quantify the solubility of corrosion products in heavy liquid metals as a function of temperature using in-situ LA-ICPMS characterization. This technique consists in putting very small corrosion cells (cell material is the steel of interest - EUROFER) in the LA-ICPMS system and measure corrosion products content (Ni, Fe, Cr) in the liquid metal. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Other, Other |