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All Journal Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Juan Carlos Sihotang
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A Review on High-Temperature Steam Oxidation Resistance of Zirconium Cladding Materials Subjected to Plasma Electrolysis Nisa Nashrah; Cahya Krisnawati Marbun; Akbar Ridho Saputra; Juan Carlos Sihotang
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 31 No. 2 (2025): Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/urania.2025.12906

Abstract

 Zirconium alloys, such as Zircaloy-4 and ZIRLO, are the standard cladding materials in pressurized water reactors (PWR) due to their low neutron absorption and corrosion resistance. Yet, under loss-of-coolant accident conditions, rapid steam oxidation above 900 °C accelerates hydrogen uptake, embrittlement, and cladding failure. Plasma electrolysis (PE) has emerged as a promising surface modification strategy, directly converting the Zr surface into a ZrO₂-based ceramic layer with strong adhesion, phase stability, and enhanced oxidation resistance. This review provides a comprehensive overview of PE coating formation, emphasizing anodic oxidation, plasma microdischarge, and incorporation of electrolyte-derived elements that tailor microstructure and tetragonal ZrO₂ stabilization. Comparative assessments show that PE-coated claddings delay breakaway oxidation, suppress oxygen diffusion, and maintain structural integrity better than bare alloys or many physical vapor–deposited coatings. The influence of coolant chemistry, irradiation effects, and thermal cycling on long-term coating durability is also evaluated. Remaining challenges include controlling thickness, mitigating phase transformation, and ensuring irradiation stability. Addressing these issues will be critical to realizing PE-coated zirconium as a viable accident-tolerant fuel cladding for advanced nuclear reactors. 
Co-Authors Akbar Ridho Saputra Cahya Krisnawati Marbun Nisa Nashrah