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Effect of P2O5 on the structure and phase separation of sodium borosilicate glasses
MinSeong Hwang, Jaeyeop Chung
J. Korean Ceram. Soc. 2024;61(2):250-257.   Published online December 6, 2023
DOI: https://doi.org/10.1007/s43207-023-00344-y
      
Reaction–diffusion bonding of CVD SiC using CrAl thin coating layer
Hyeon‑Geun Lee, Daejong Kim, Weon-Ju Kim, Ji Yeon Park
J. Korean Ceram. Soc. 2022;59(1):113-123.   Published online January 31, 2022
DOI: https://doi.org/10.1007/s43207-021-00162-0
         Cited By 1
A review on the joining of SiC for high‑temperature applications
Dang‑Hyok Yoon, Ivar E. Reimanis
J. Korean Ceram. Soc. 2020;57(3):246-270.   Published online March 31, 2020
DOI: https://doi.org/10.1007/s43207-020-00021-4
         Cited By 43
Functional Li-M (Ti, Al, Co, Ni, Mn, Fe)-O Energy Materials
In Yea Kim, Seo Yoon Shin, Jea Hwan Ko, Kang Soo Lee, Sung Pil Woo, Dong Kyu Kim, Young Soo Yoon
J. Korean Ceram. Soc. 2017;54(1):9-22.   Published online January 31, 2017
DOI: https://doi.org/10.4191/kcers.2017.54.1.11
                           Cited By 17
Glass Property Models, Constraints, and Formulation Approaches for Vitrification of High-Level Nuclear Wastes at the US Hanford Site
Dongsang Kim
J. Korean Ceram. Soc. 2015;52(2):92
DOI: https://doi.org/10.4191/kcers.2015.52.2.92
         Cited By 25
Influence of Winding Patterns and Infiltration Parameters on Chemical Vapor Infiltration Behaviors of SiCf/SiC Composites
Daejong Kim, Myoungjin Ko, Hyeon-Geun Lee, Ji Yeon Park, Weon-Ju Kim
J. Korean Ceram. Soc. 2014;51(5):453
DOI: https://doi.org/10.4191/kcers.2014.51.5.453
         Cited By 1
FEA Study on Hoop Stress of Multilayered SiC Composite Tube for Nuclear Fuel Cladding
Hyeon-Geun Lee, Daejong Kim, Ji Yeon Park, Weon-Ju Kim
J. Korean Ceram. Soc. 2014;51(5):435
DOI: https://doi.org/10.4191/kcers.2014.51.5.435
         Cited By 2
Sintering and Characterization of SiC-matrix Composite Including TRISO Particles
Hyeon-Geun Lee, Daejong Kim, Ji Yeon Park, Weon-Ju Kim
J. Korean Ceram. Soc. 2014;51(5):418
DOI: https://doi.org/10.4191/kcers.2014.51.5.418
         Cited By 2
Oxidation Behavior and Property Changes of Nuclear Graphite
Kwang-Youn Cho, Kyong-Ja Kim, Yun-Soo Lim, Yun-Joong Chung, Se-Hwan Chi
J. Korean Ceram. Soc. 2006;43(12):833
DOI: https://doi.org/10.4191/kcers.2006.43.12.833
         Cited By 2
Oxidation Behavior of Nuclear Graphite(IG110) with Surface Roughness
Kwang-Youn Cho, Kyong-Ja Kim, Yun-Soo Lim, Se-Hwan Chi
J. Korean Ceram. Soc. 2006;43(10):613
DOI: https://doi.org/10.4191/kcers.2006.43.10.613
         Cited By 9
Fracture Properties of Nuclear Graphite Grade IG-110
Dong-Yun Han, Eung-Sun Kim, Se-Hwan Chi, Yun-Soo Lim
J. Korean Ceram. Soc. 2006;43(7):439
DOI: https://doi.org/10.4191/kcers.2006.43.7.439
         Cited By 4
Fabrication and Ion Irradiation Characteristics of SiC-Based Ceramics for Advanced Nuclear Energy Systems
Weon-Ju Kim, Seok-Min Kang, Kyeong-Hwan Park, Kohyama Akira , Woo-Seog Ryu, Ji-Yeon Park
J. Korean Ceram. Soc. 2005;42(8):575
DOI: https://doi.org/10.4191/kcers.2005.42.8.575
         Cited By 12
Pore Size and its Distribution as a Function of Sintered Density of UO2-20 wt%CeO2Pellets
나상호, 김기홍, 김시형, 이영우, 유명준
J. Korean Ceram. Soc. 2003;40(6):572
DOI: https://doi.org/10.4191/kcers.2003.40.6.572
      
Uranium Recovery from Nuclear Fuel Powder Conversion Plant Filtrate and its Thermal Decomposition Characteristics
Kyung-Chai Jeong, Ji-Young Jeong, Byung-Ho Kim, Tae-Joon Kim, Jong-Hyeun Choi
J. Korean Ceram. Soc. 2002;39(2):204
DOI: https://doi.org/10.4191/kcers.2002.39.2.204
      
NaF Preparation from the Waste for Nuclear Fuel Powder Production Process
정경채, 정원명, 김응호, 박진호, 황성태
J. Korean Ceram. Soc. 1996;33(8):953
      
Powder Characteristics by Change of Reacting Material in Nuclear Fuel Powder Preparation
정경채, 박진호, 황성태
J. Korean Ceram. Soc. 1996;33(6):631
      
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