Recent research progress on the compatibility of tritium breeders with structural materials and coatings in fusion reactors

C Wang, BL Ji, SX Gu, Q Qi, L Chen, HS Zhou, SL Liu… - Tungsten, 2022 - Springer
Nuclear fusion energy is considered as a clean and safe energy source. As the fuel of
deuterium–tritium (D–T) fusion reactor, T must be produced by the reaction between neutron …

Fabrication of eutectic FeCrCoNiV1. 5 high entropy alloy coating with excellent high-temperature wear resistance

M He, H Kang, G Hou, Z Lian, S Lu, Y Li, W Qin… - Surface and Coatings …, 2024 - Elsevier
Developing wear resistant protective coatings on ferritic/martensitic steel (F/M) used in fourth
generation nuclear reactor is still a challenge, especially at high-temperature service …

Impressive high-temperature oxidation resistance of FeCrNiMnAl high entropy alloy coating on the ferritic/martensitic steel with primordial Al2O3 and Mn3O4 gradient …

M He, H Kang, S Lin, Y Liu, P Zhang, W Qin… - Journal of Alloys and …, 2022 - Elsevier
Recently, ferritic/martensitic steel (F/M) has been widely used in the fields of thermal power
unit and nuclear energy. While the disadvantage of insufficient oxidation resistance at high …

Hydrogen permeation from F82H wall of ceramic breeder pebble bed: The effect of surface corrosion

K Mukai, S Kenjo, N Iwamatsu, B Mahmoud… - International Journal of …, 2022 - Elsevier
Understanding the permeation behavior of tritium from a pebble bed breeding blanket is
essential for establishing a self-sufficient fuel cycle in a nuclear fusion reactor. It is known …

[HTML][HTML] Comparative analysis of low cycle fatigue behavior of pre-corroded standard and sub-sized EUROFER97 specimens exposed to ceramic breeder …

E Gaisina, R Gaisin, J Leys, R Knitter, J Aktaa… - Nuclear Materials and …, 2023 - Elsevier
In the helium-cooled pebble bed blanket concept of DEMO, the reduced activation ferritic-
martensitic steel EUROFER97 will be in direct contact with lithium ceramic pebbles and …

Lithium-lead corrosion behavior of zirconium oxide coating after heavy-ion irradiation

S Miura, K Nakamura, E Akahoshi, S Kano… - Fusion Engineering and …, 2021 - Elsevier
For a strict control of tritium migration in fusion reactor fuel systems, tritium permeation
barrier coatings have been developed for several decades. In liquid blanket concepts …

Corrosiveness of Li2TiO3 ceramic tritium breeder to structural RAFM steel: Effects on microstructure and thermal conductivity

C Wang, B Ji, S Gu, Q Qi, H Zhou, GN Luo - Ceramics International, 2023 - Elsevier
Structural steel will be in long-term contact with ceramic tritium breeder at a high
temperature in a solid tritium breeding blanket. The maximum temperature in the tritium …

Deuterium permeation through multi-layer ceramic coatings under liquid lithium-lead exposure condition

E Akahoshi, M Matsunaga, K Kimura, K Nakamura… - Corrosion …, 2021 - Elsevier
Corrosion of tritium permeation barrier ceramic coatings by liquid tritium breeders is an
unavoidable concern in a high thermal efficiency fusion reactor. In this study, we have …

Study on the chemical compatibility between Li2TiO3 ceramic pebbles and diverse advanced structural materials

G Tan, X Hu, L Cai, H Xue, Y Oya… - International Journal of …, 2023 - Wiley Online Library
The tritium breeder and structural materials are necessary components in the blanket to
realize tritium (T) self‐sustainment of nuclear fusion. The long‐term exposure between …

Fabrication and characterization of zirconium oxide coating on tubular steel by metal organic decomposition

K Do Duy, R Norizuki, H Fujiwara, K Shirota… - Journal of Nuclear …, 2024 - Elsevier
In fusion reactor blankets, multifunctional ceramic coatings fabricated on structural materials
have been investigated for tritium permeation reduction, electrical insulation, and corrosion …