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- [2] Corrosion behavior of zirconium alloy fuel assembly cladding tubes in the pressurized water reactor?s primary circuit INTERNATIONAL JOURNAL OF CORROSION AND SCALE INHIBITION, 2022, 11 (04): : 1628 - 1638
- [4] Chemical interaction layer between uranium oxide fuel pellet and zirconium alloy cladding in pressurized water reactor He Jishu/Nuclear Techniques, 2023, 46 (09):
- [6] Effect of polyacrylic acid on the corrosion behavior of Alloy 690 in pressurized water reactor secondary water JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY, 2025, 220 : 1 - 13
- [7] Research progress of chromium coating on zirconium alloy for nuclear fuel cladding Surface Technology, 2021, 50 (01): : 221 - 231
- [10] Evolution of fretting wear behavior of zirconium alloy cladding tube under gross slip regime in simulated primary water of pressurized water reactor JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY, 2025, 220 : 276 - 289