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Corrosion Behavior of Zr-Nb Alloys in 360 ^oC Water and 500^oC Supercritical Water

Park, J.-Y.; Kim, H.-G.; Jeong, Y. H.

Metals and materials international. VOL 12; PART 6, ; 2006, 497-504 -- Hanrimwon Publishing Co. Part: Part 6; (pages 497-504) -- 2006

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Phase boundary of the Zr-rich region in commercial grade Zr–Nb alloys

Kim, H. G.; Park, J. Y.; Jeong, Y. H.

Journal of nuclear materials. VOL 347; NUMBER 1-2, ; 2005, 140-150 -- Elsevier Science B.V., Amsterdam. (pages 140-150) -- 2005

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Ex-reactor corrosion and oxide characteristics of Zr–Nb–Fe alloys with the Nb/Fe ratio

Kim, H. G.; Park, J. Y.; Jeong, Y. H.

Journal of nuclear materials. VOL 345; NUMBER 1, ; 2005, 1-10 -- Elsevier Science B.V., Amsterdam. (pages 1-10) -- 2005

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2138 Ductile-to-Brittle Transition Behavior of the HANA Claddings after LOCA Simulated Oxidation and Water Quenching Test

Kim, H.-G.|Park, J.-Y.|Jeong, Y.-H.

Paris; SFEN; 2009 -- Volume: 1 (pages 567-572) -- 2009

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1066 Effect of the Nb/Fe Ratio on Corrosion and Oxide Characteristics of Zr-xNb-yFe Alloys

Jeong, Y. H.; Kim, H. G.; Park, J. Y.

Proceedings of the ... international meeting on LWR fuel performance; LWR fuel performance; Orlando, FL, 2004; Sep, 0, 348-355 -- La Grange Park:; ANS,; 2004 (pages 348-355)

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Parameter study for manufacturing an inner and outer cladding tube used in dual-cooled annular fuel

Kim, H. G. et al.

Nuclear engineering and design. VOL 248, ; 2012, 35-41 -- Elsevier Science B.V., Amsterdam. Part: Part; (pages 35-41) -- 2012

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In situ heating TEM analysis of oxide layer formed on Zr–1.5Nb alloy

Kim, H. G. et al.

Journal of nuclear materials. VOL 451; NUMBER 1-3, ; 2014, 189-197 -- Elsevier Science B.V., Amsterdam. Part 1-3; (pages 189-197) -- 2014

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Microstructures of diffusion bonded SiC ceramics using Ti and Mo interlayers

Jung, Y. I. et al.

Journal of nuclear materials. VOL 441; NUMBER 1-3, ; 2013, 510-513 -- Elsevier Science B.V., Amsterdam. Part 1-3; (pages 510-513) -- 2013

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Microstructures of laser bonded SiC ceramics with Zr interlayers

Jung, Y. I. et al.

Journal of nuclear materials. VOL 455; NUMBER 1/3, ; 2014, 586-590 -- Elsevier Science B.V., Amsterdam. Part 1/3; (pages 586-590) -- 2014

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Evaluation of Hydride Effect on Fuel Cladding Degradation

Kim, H.-G. et al.

JOURNAL- KOREAN INSTITUTE OF METALS AND MATERIALS. VOL 48; PART 8, ; 2010, 717-723 -- KOREAN INSTITUTE OF METALS AND MATERIALS (pages 717-723) -- 2010

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  1. Kim, H.‐G.
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  5. Kim, I. H.

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