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PROPERTIES OF ZR ALLOY CLADDING AFTER SIMULATED LOCA OXIDATION AND WATER QUENCHING
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  • PROPERTIES OF ZR ALLOY CLADDING AFTER SIMULATED LOCA OXIDATION AND WATER QUENCHING
  • PROPERTIES OF ZR ALLOY CLADDING AFTER SIMULATED LOCA OXIDATION AND WATER QUENCHING
저자명
Kim. Hyun-Gil,Kim. Il-Hyun,Jung. Yang-Il,Park. Jeong-Yong,Jeong. Yong-Hwan
간행물명
Nuclear engineering and technology : an international journal of the Korean Nuclear Society
권/호정보
2010년|42권 2호|pp.193-202 (10 pages)
발행정보
한국원자력학회
파일정보
정기간행물|ENG|
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기타
이 논문은 한국과학기술정보연구원과 논문 연계를 통해 무료로 제공되는 원문입니다.
서지반출

기타언어초록

In order to study the cladding properties of zirconium after a loss-of-coolant accident (LOCA)-simulation oxidation and water quenching test, commercial Zircaloy-4 and two kinds of HANA claddings were oxidized at temperatures ranging from $900^{circ}C$ to $1250^{circ}C$ and exposed for 300 s, and then cooled to $700^{circ}C$ before quenching. Microstructural observations were made to evaluate the matrix characteristics with the chemical compositions after the LOCA-simulation test. Ring compression testing was then performed to compare the ductile behaviour of the HANA and Zircaloy-4 claddings. An X-ray diffraction (XRD) analysis was carried out for temperatures ranging from room temperature to $1250^{circ}C$ for the oxide layer to verify the oxide crystal structure at each oxidation temperature.