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IN-PILE PERFORMANCE OF HANA CLADDING TESTED IN HALDEN REACTOR
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  • IN-PILE PERFORMANCE OF HANA CLADDING TESTED IN HALDEN REACTOR
  • IN-PILE PERFORMANCE OF HANA CLADDING TESTED IN HALDEN REACTOR
저자명
Kim. Hyun-Gil,Park. Jeong-Yong,Jeong. Yong-Hwan,Koo. Yang-Hyun,Yoo. Jong-Sung,Mok. Yong-Kyoon,Kim. Yoon-Ho,Suh. Jung-Min
간행물명
Nuclear engineering and technology : an international journal of the Korean Nuclear Society
권/호정보
2014년|46권 3호|pp.423-430 (8 pages)
발행정보
한국원자력학회
파일정보
정기간행물|ENG|
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기타
이 논문은 한국과학기술정보연구원과 논문 연계를 통해 무료로 제공되는 원문입니다.
서지반출

기타언어초록

An in-pile performance test of HANA claddings was conducted at up to 67 GWD/MTU in the Halden research reactor in Norway over a 6.5 year period. Four types of HANA claddings (HANA-3, HANA-4, HANA-5, and HANA-6) and a reference Zircaloy-4 cladding were used for the in-pile test. The evaluation parameters of the HANA claddings were the corrosion behavior, dimensional changes, hydrogen uptake, and tensile strength after the claddings were tested under the simulated operation conditions of a Korean commercial reactor. The oxide thickness ranged from 15 to 37 mm at a high flux region in the test rods, and all HANA claddings showed corrosion resistance superior to the Zircaloy-4 cladding. The creep-down rate of all HANA claddings was lower than that of the Zircaloy-4 cladding. In addition, the hydrogen content of the HANA claddings ranged from 54 to 96 wppm at the high heat flux region of the test rods, whereas the hydrogen content of the Zircaloy-4 cladding was 119 wppm. The tensile strength of the HANA and Zircaloy-4 claddings was similarly increased when compared to the un-irradiated claddings owing to the radiation-induced hardening.