Analysis of Thermal Shock Behavior of Cladding with SiCf/SiC Composite Protective Films

• Journal title : Composites Research
• Volume 29, Issue 1,  2016, pp.40-44
• Publisher : The Korean Society for Composite Materials
• DOI : 10.7234/composres.2016.29.1.040
Title & Authors
Analysis of Thermal Shock Behavior of Cladding with SiCf/SiC Composite Protective Films
Lee, Dong-Hee; Kim, Weon-Ju; Park, Ji-Yeon; Kim, Dae-Jong; Lee, Hyeon-Geon; Park, Kwang-Heon;

Abstract
Nuclear fuel cladding used in a nuclear power plant must possess superior oxidation resistance in the coolant atmosphere of high temperature/high pressure. However, as was the case for the critical LOCA (loss-of-coolant accident) accident that took place in the Fukushima disaster, there is a risk of hydrogen explosion when the nuclear fuel cladding and steam reacts dramatically to cause a rapid high-temperature oxidation accompanied by generation of a huge amount of hydrogen. Hence, an active search is ongoing for an alternative material to be used for manufacturing of nuclear fuel cladding. Studies are currently aimed at improving the safety of this cladding. In particular, ceramic-based nuclear fuel cladding, such as SiC, is receiving much attention due to the excellent radiation resistance, high strength, chemical durability against oxidation and corrosion, and excellent thermal conduction of ceramics. In the present study, cladding with $\small{SiC_f/SiC}$ protective films was fabricated using a process that forms a matrix phase by polymer impregnation of polycarbosilane (PCS) after filament-winding the SiC fiber onto an existing Zry-4 cladding tube. It is analyzed the oxidation and microstructure of the metal cladding with $\small{SiC_f/SiC}$ composite protective films using a drop tube furnace for thermal shock test.
Keywords
$\small{SiC_f/SiC}$ composite;Thermal shock;Fuel cladding;Polymer impregnation and pyrolysis;
Language
Korean
Cited by
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