6 results on '"Peng, Zhenxun"'
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2. Fretting wear mechanism of nuclear fuel cladding tube under different tangential displacement
3. Isothermal experiments on eutectic and oxidation reactions of Cr-coated Zr alloy cladding in steam at 1350 ℃: Behavior, mechanism and kinetics
4. Fretting wear behaviors of Cr-coated Zr–1Nb alloy cladding tube mated with Zr-4 alloy dimple under different tangential displacements
5. Fretting corrosion behavior of a Cr-coated Zr-1Nb alloy cladding in simulated PWR primary water environment.
6. Oxidation behavior and kinetics of magnetron-sputtered Cr-coated Zr alloy cladding in 1000–1300 ℃ steam environment.
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