Researchers at the Institute of Science Tokyo, in collaboration with Yokohama National University, Nippon Nuclear Fuel Development, and the National Institute for Fusion Science, tested Oxide Dispersion Strengthened (ODS) alloys with liquid metal flow at 1112°F (600°C) to simulate a fusion blanket environment.
The anti-corrosive properties of the alloys demonstrated in these tests will help develop the material durability of nuclear fusion reactors.
Nuclear fusion is expected to play a major role in this energy transition as the world works to phase out fossil fuels and turn to cleaner energy sources. Unlike its fission counterpart, nuclear fusion does not produce radioactive waste. The process replicates the reactions that occur in the Sun and, therefore, requires extremely high temperatures.
This requires using advanced materials and liquid metal coolants to extract heat from the reactor when necessary. However, these coolants, typically made from lithium and lithium-lead (LiPb) alloys, are highly corrosive and threaten the structural integrity of the reactor vessel. This is where ODS alloys can help.
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