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      SCOPUS KCI등재

      Development of Innovative Light Water Reactor Nuclear Fuel Using 3D Printing Technology

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      https://www.riss.kr/link?id=A101891490

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      다국어 초록 (Multilingual Abstract)

      To enhance the safety of nuclear reactors after the Fukushima accident, researchers are developing various types of accident tolerant fuel (ATF) to increase the coping time and reduce the generation of hydrogen by oxidation. Coated cladding, an ATF co...

      To enhance the safety of nuclear reactors after the Fukushima accident, researchers are developing various types of accident tolerant fuel (ATF) to increase the coping time and reduce the generation of hydrogen by oxidation. Coated cladding, an ATF concept, can be a promising technology in view of its commercialization. We applied 3D printing technology to the fabrication of coated cladding as well as of coated pellets. Direct metal tooling (DMT) in 3D printing technologies can create a coated layer on the tubular cladding surface, which maintains stability during corrosion, creep, and wear in the reactor. A 3D laser coating apparatus was built, and parameter studies were carried out. To coat pellets with erbium using this apparatus, we undertook preliminary experiments involving metal pellets. The adhesion test showed that the coated layer can be maintained at near fracture strength.

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      참고문헌 (Reference)

      1 Al-Olayyan, Y., "The Effect of Zircaloy-4 Substrate Surface Condition on the Adhesion Strength and Corrosion of SiC Coatings" 346 (346): 109-119, 2005

      2 Wekipedia, "Selective Laser Sintering"

      3 Kim, H. C., "Principle and Recent Trend of Rapid Prototyping Technology" 14 (14): 187-199, 2005

      4 Brachet, J. C., "Microstructure and Properties of a 3-Layers Nuclear Fuel Cladding Prototype Containing Erbium as a Neutronic Burnable Poison" 2013

      5 Nieuwenhove, R. V., "Investigation of the Impact of Coatings on Corrosion and Hydrogen Uptake of Nuclear Components" 2014

      6 Lamarsh, J. R., "Introduction to Nuclear Engineering" Prentice-Hall 2012

      7 Kim, S. W., "Incore Fuel Management" 44 (44): 2010

      8 Hu, X., "Hydrogen Permeation in FeCrAl Alloys for LWR Cladding Application" 461 : 282-291, 2015

      9 Kim, H. G., "High-Temperature Oxidation Behavior of Cr-Coated Zirconium Alloy" 842-846, 2013

      10 Bragg-Sitton, S., "Development of Advanced Accident-Tolerant Fuels for Commercial LWRs"

      1 Al-Olayyan, Y., "The Effect of Zircaloy-4 Substrate Surface Condition on the Adhesion Strength and Corrosion of SiC Coatings" 346 (346): 109-119, 2005

      2 Wekipedia, "Selective Laser Sintering"

      3 Kim, H. C., "Principle and Recent Trend of Rapid Prototyping Technology" 14 (14): 187-199, 2005

      4 Brachet, J. C., "Microstructure and Properties of a 3-Layers Nuclear Fuel Cladding Prototype Containing Erbium as a Neutronic Burnable Poison" 2013

      5 Nieuwenhove, R. V., "Investigation of the Impact of Coatings on Corrosion and Hydrogen Uptake of Nuclear Components" 2014

      6 Lamarsh, J. R., "Introduction to Nuclear Engineering" Prentice-Hall 2012

      7 Kim, S. W., "Incore Fuel Management" 44 (44): 2010

      8 Hu, X., "Hydrogen Permeation in FeCrAl Alloys for LWR Cladding Application" 461 : 282-291, 2015

      9 Kim, H. G., "High-Temperature Oxidation Behavior of Cr-Coated Zirconium Alloy" 842-846, 2013

      10 Bragg-Sitton, S., "Development of Advanced Accident-Tolerant Fuels for Commercial LWRs"

      11 Stempien, J. D., "Characteristics of Composite Silicon Carbide Fuel Cladding after Irradiation under Simulated PWR Conditions" 183 (183): 13-29, 2013

      12 Idarraga-Trujillo, I., "Assessment at CEA of Coated Nuclear Fuel Cladding for LWRs with Increased Margins in LOCA and Beyond LOCA Conditions" 860-867, 2013

      13 Kim, H. G., "Adhesion Property and High-Temperature Oxidation Behavior of Cr-Coated Zircaloy-4Cladding Tube Prepared by 3D Laser Coating" 465 : 531-539, 2015

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      학술지 이력

      학술지 이력
      연월일 이력구분 이력상세 등재구분
      2023 평가예정 해외DB학술지평가 신청대상 (해외등재 학술지 평가)
      2020-01-01 평가 등재학술지 유지 (해외등재 학술지 평가) KCI등재
      2013-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2010-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2008-06-23 학회명변경 영문명 : Korean Society Of Precision Engineering -> Korean Society for Precision Engineering KCI등재
      2008-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2006-07-07 학술지명변경 외국어명 : 미등록 -> Journal of the Korean Society for Precision Engineering KCI등재
      2006-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2004-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2001-01-01 평가 등재학술지 선정 (등재후보2차) KCI등재
      1998-07-01 평가 등재후보학술지 선정 (신규평가) KCI등재후보
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      학술지 인용정보

      학술지 인용정보
      기준연도 WOS-KCI 통합IF(2년) KCIF(2년) KCIF(3년)
      2016 0.26 0.26 0.26
      KCIF(4년) KCIF(5년) 중심성지수(3년) 즉시성지수
      0.24 0.22 0.449 0.12
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