INVESTIGATION ON OXIDATION BEHAVIORS OF FECRAL ALLOY CLADDING UNDER THE SIMULATED LOCA CONDITIONS

被引:0
|
作者
Chen, Kang [1 ]
Du, Zhengang [1 ,2 ]
Wen, Qinglong [1 ,2 ]
Zhang, Ruiqian [3 ]
机构
[1] Chongqing Univ, Sch Energy & Power Engn, Dept Nucl Engn & Technol, Chongqing 400044, Peoples R China
[2] Chongqing Univ, Key Lab Low Grade Energy Utilizat Technol & Syst, Chongqing 400044, Peoples R China
[3] Nucl Power Inst China, Key Lab Reactor Fuel & Mat, Chengdu 610213, Peoples R China
基金
中国国家自然科学基金;
关键词
LOCA; ATF; FeCrAl alloy cladding; oxidation behavior; HIGH-TEMPERATURE OXIDATION; CANDIDATE MATERIALS; STEAM;
D O I
暂无
中图分类号
TE [石油、天然气工业]; TK [能源与动力工程];
学科分类号
0807 ; 0820 ;
摘要
During a LOCA (Loss of Coolant Accident), the zirconium alloy cladding undergoes oxidation, generating significant heat and hydrogen gas. In extreme circumstances, this can result in hydrogen explosions compromising reactor safety. Recently, the ATF (Accident Tolerant Fuel) cladding has been introduced as a new generation of fuel cladding. Among the ATF claddings, FeCrAl alloy cladding exhibits a low oxidation rate during LOCA due to the formation of a dense alumina layer during high-temperature oxidation. However, current research on this FeCrAl alloy cladding remains limited in scope and depth. The present study focuses on the oxidation behavior of FeCrAl alloy cladding at 1200 degrees C in steam. Key findings include: (1) Spots on the sample were identified as oxides of Fe, Cr, and Al through microscopic analysis. (2) An oxide layer of Al was observed with a thickness ranging from 0.86 mu m to 1.98 mu m. (3) The ring compression test revealed that the FeCrAl alloy cladding neither fractured nor underwent a ductile- brittle transition.
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页数:6
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