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논문 기본 정보

자료유형
학술저널
저자정보
안동현 (한국원자력연구원) 이종연 (한국원자력연구원) 최민재 (한국원자력연구원) 김종민 (한국원자력연구원) 김성우 (한국원자력연구원) 우완측 (한국원자력연구원)
저널정보
한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology Vol.56 No.2
발행연도
2024.2
수록면
506 - 519 (14page)
DOI
10.1016/j.net.2023.10.027

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To simulate the verification process using materials from a decommissioned reactor, a mock-up of the bottommounted instrument nozzle in the Kori 1 reactor, where the nozzle was attached to a plate by J-groove dissimilar metal welding, was fabricated. The mock-up distortion was quantified by measuring the plate surface displacement after welding. The residual stresses formed on the support plate surface and the inner surface of the nozzle were then analyzed using the hole-drilling method, contour method, and neutron diffraction. Welding simulations were performed using a 3D finite element method to validate the measured results. The measured and computed stress distributions on the support plate exhibited reasonable agreement. Conversely, the stresses on the inside of the nozzle were found to have an indisputable difference in the contour method and neutron diffraction measurements, which demonstrated strong tensile and compressive hoop stresses, respectively. The possible origins of such differences were investigated and we have provided some suggestions for a precise evaluation in the simulation. This study is expected to be useful in future research on decommissioned reactors.

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