Title :
Study and Assessment of Zry Cladding Oxidation Model under Severe Accident in PWR
Author :
Shi Xingwei ; Cao Xinrong
Author_Institution :
Nat. Defense Key Subject Lab. of Nucl. Safety & Simulation Tech., Harbin Eng. Univ., Harbin, China
Abstract :
This paper summarizes the earlier and the most advanced correlations of zirconium alloy cladding oxidation in steam at high temperature. A good combination of correlations applied in calculation more widely has been found by comparison and assessment of existing Zry oxidation kinetics correlations within the Zr-4 cladding tube oxidation experiment.
Keywords :
fission reactor fuel claddings; nuclear power stations; oxidation; zirconium alloys; PWR; Zr-4 cladding tube oxidation experiment; Zry cladding oxidation model; Zry oxidation kinetics correlation; zirconium alloy cladding oxidation; Correlation; Fuels; Metals; Oxidation; Temperature distribution; Temperature measurement; Zirconium;
Conference_Titel :
Power and Energy Engineering Conference (APPEEC), 2011 Asia-Pacific
Conference_Location :
Wuhan
Print_ISBN :
978-1-4244-6253-7
DOI :
10.1109/APPEEC.2011.5748921
