The effect of Li 2 TiO 3 pebbles on the mechanical properties of ARAA under breeding blanket conditionsopen access
- Authors
- Jung, Yunsong; Park, Youngah; Ku, Duck Young; Park, Yi-Hyun; Gwon, Hyoseong
- Issue Date
- Jun-2024
- Publisher
- ELSEVIER
- Keywords
- Breeding blanket; Compatibility; RAFM; ARAA; Li2TiO3
- Citation
- NUCLEAR MATERIALS AND ENERGY, v.39
- Journal Title
- NUCLEAR MATERIALS AND ENERGY
- Volume
- 39
- URI
- https://scholarworks.bwise.kr/gachon/handle/2020.sw.gachon/92027
- DOI
- 10.1016/j.nme.2024.101658
- ISSN
- 2352-1791
2352-1791
- Abstract
- The breeding blanket serves as a critical element for achieving a self-sustaining tritium cycle and generating sufficient energy in fusion reactors. This study focuses on candidate materials of the helium-cooled solid breeder blanket designed for a demonstration fusion reactor breeding blanket in Korea. We conducted compatibility tests between advanced reduced-activation alloy (ARAA) and Li 2 TiO 3 pebbles at 550 degrees C for 28 days in He -0.1 vol% H 2 purge gas conditions. Surface oxidation on ARAA was observed regardless of pebble presence. Double oxide films comprised of Fe-rich and Cr-rich layers formed on the surface of ARAA with pebbles. Lithium deposition was verified in both contact and non -contact areas of ARAA. Despite surface oxidation, the impact on tensile strength and elongation was found to be negligible.
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