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    KCI등재 SCI SCIE SCOPUS

    Development of Fabrication and Qualification Methods for the First Wall of the International Thermonuclear Experimental Reactor

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    https://www.riss.kr/link?id=A104335097

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    다국어 초록 (Multilingual Abstract) kakao i 다국어 번역

    In order to investigate the manufacturing and qualification methods for the first wall (FW) of the
    International Thermonuclear Experimental Reactor (ITER), we fabricated several mock-ups with
    various shapes through the hot isostatic pressing (HIP) bonding method for joining the Cu-alloy
    with Be armor and the Cu-alloy with stainless steel (SS). Non-destructive test (NDT) methods
    currently being developed for the ITER FW were applied to these mock-ups to find the defects.
    Ultrasonic test (UT) showed that a probe of 10 MHz and 0.25 inch in diameter could detect defects
    up to 3 mm in diameter. The eddy current test (ECT) for the SS tube was simulated with a
    numerical code and showed the feasibility of detecting defects in the SS tube. Thermography was
    simulated with a numerical code, CFX-10, and preliminary tests were performed. Also, a high heat
    flux (HHF) test was performed up to 1000 cycles at 5.0 MW/m2 for the Cu/SS mock-up in Japan
    (JEBIS, JAEA Electron Beam Irradiation Stand), and it is being prepared for the Be/Cu mock-up
    in Russia.
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    In order to investigate the manufacturing and qualification methods for the first wall (FW) of the International Thermonuclear Experimental Reactor (ITER), we fabricated several mock-ups with various shapes through the hot isostatic pressing (HIP) b...

    In order to investigate the manufacturing and qualification methods for the first wall (FW) of the
    International Thermonuclear Experimental Reactor (ITER), we fabricated several mock-ups with
    various shapes through the hot isostatic pressing (HIP) bonding method for joining the Cu-alloy
    with Be armor and the Cu-alloy with stainless steel (SS). Non-destructive test (NDT) methods
    currently being developed for the ITER FW were applied to these mock-ups to find the defects.
    Ultrasonic test (UT) showed that a probe of 10 MHz and 0.25 inch in diameter could detect defects
    up to 3 mm in diameter. The eddy current test (ECT) for the SS tube was simulated with a
    numerical code and showed the feasibility of detecting defects in the SS tube. Thermography was
    simulated with a numerical code, CFX-10, and preliminary tests were performed. Also, a high heat
    flux (HHF) test was performed up to 1000 cycles at 5.0 MW/m2 for the Cu/SS mock-up in Japan
    (JEBIS, JAEA Electron Beam Irradiation Stand), and it is being prepared for the Be/Cu mock-up
    in Russia.

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    참고문헌 (Reference)

    1 "ITER Material Properties Handbook, File code: ITERAA02-2402 (www.iter.org)."

    1 "ITER Material Properties Handbook, File code: ITERAA02-2402 (www.iter.org)."

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    학술지 이력

    학술지 이력
    연월일 이력구분 이력상세 등재구분
    2023 평가 해외DB학술지평가 신청대상 (해외등재 학술지 평가)
    2020-01-01 등재 등재학술지 유지 (해외등재 학술지 평가) KCI등재
    2011-01-01 등재 등재학술지 유지 (등재유지) KCI등재
    2009-01-01 등재 등재학술지 유지 (등재유지) KCI등재
    2007-01-01 등재 SCI 등재 (등재유지) KCI등재
    2005-01-01 등재 등재학술지 유지 (등재유지) KCI등재
    2002-07-01 등재 등재학술지 선정 (등재후보2차) KCI등재
    2000-01-01 등재 등재후보학술지 선정 (신규평가) KCI등재후보
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    학술지 인용정보

    학술지 인용정보
    기준연도 WOS-KCI 통합IF(2년) KCIF(2년) KCIF(3년)
    2016 0.47 0.15 0.31
    KCIF(4년) KCIF(5년) 중심성지수(3년) 즉시성지수
    0.26 0.2 0.26 0.03
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