journal article·2026-02

High-resolution characterization of ceramic-metal interface of TiN coating on ferritic-steels for nuclear application

Yuhan Li, Chao Jiang, Tiankai Yao, Haiyan Wang, Jian Gan

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OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Nuclear reactor physics and engineering

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References (20)

Show source-provided references
1. Metal fuel-cladding interaction
2. Metal fuel-cladding interaction
3. Fuel-cladding chemical interaction in U-Pu-Zr metallic fuels: a critical review10.1080/00295450.2017.1323535 ↗
4. Fast neutron irradiation capability in existing thermal test reactors10.1016/j.anucene.2024.110731 ↗
5. Titanium surface nitriding by sodium amide in molten salts
6. An innovative radial gradient material design using hot isostatic pressing for applications in extreme environments10.1016/j.jmapro.2025.07.059 ↗
7. Effect of TiN coating on suppressing Ce-Fe interaction under irradiation10.1016/j.mtla.2024.102221 ↗
8. Improved radiation damage tolerance of titanium nitride ceramics by introduction of vacancy defects10.1016/j.jeurceramsoc.2013.10.012 ↗
9. Tin coating of tool steels: a review10.1016/0924-0136(93)90016-Y ↗
10. Room-temperature industrially-scaled pulsed laser deposition of coatings for wear-protection, low-friction and decorative applications
11. TiN-based coatings on fuel cladding tubes for advanced nuclear reactors10.1016/j.jnucmat.2012.05.001 ↗
12. Interface adhesion: effects of plasticity and segregation10.1016/S1359-6454(99)00269-4 ↗
13. Ceramic/metal interface structures and their relationship to atomic- and meso-scale properties10.1016/j.mser.2003.09.001 ↗
14. SRIM – The stopping and range of ions in matter (2010)10.1016/j.nimb.2010.02.091 ↗
15. On the use of SRIM for computing radiation damage exposure10.1016/j.nimb.2013.05.008 ↗
16. Modeling injected interstitial effects on void swelling in self-ion irradiation experiments10.1016/j.jnucmat.2015.10.002 ↗
17. Microstructural evolution of ferritic-martensitic steels irradiated in the fast breeder reactor Phenix10.1016/0022-3115(93)90080-I ↗
18. Irradiation effects of HT-9 martensitic steels10.5516/NET.07.2013.706 ↗
19. HT9 swelling in high burnup fast reactor fuel pin components10.1016/j.jnucmat.2019.03.053 ↗
20. TiN inducing ferrite nucleation based on the bcc-Fe/TiN interfaces formation at atomic scale by first-principles calculation10.1016/j.commatsci.2021.110570 ↗