Preparation of U–Zr–Mn, a Surrogate Alloy for Recycling Fast Reactor Fuel von Kim, Jong-Hwan, Lee, Chan Bock, Kim, Kihwan

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Application of high-temperature ceramic plasma-spray coatings for a reusable melting crucible von Kim, Ki-Hwan, Kim, Jong Hwan, Hong, Ki-Won, Park, Jeong-Yong, Lee, Chan-Bock

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Ceramic plasma‐spray‐coated graphite crucible for injection casting of fast reactor fuel slugs von Kim, Ki‐Hwan, Hong, Ki‐Won, Kim, Jong‐Hwan, Park, Jeong‐Yong, Lee, Chan‐Bock

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Protective yttria coatings of melting crucible for metallic fuel slugs von Kim, Jong-Hwan, Song, Hoon, Kim, Ki-Hwan, Lee, Chan-Bock

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Microstructural characterization of U-Zr alloy fuel slugs for sodium-cooled fast reactor von Kim, Ki-Hwan, Oh, Seok-Jin, Kim, Sun-Ki, Lee, Chong-Tak, Lee, Chan-Bock

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Sodium fast reactor evaluation: Core materials von Cheon, Jin Sik, Lee, Chan Bock, Lee, Byoung Oon, Raison, J.P., Mizuno, T., Delage, F., Carmack, J.

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Performance of FCCI barrier foils for U–Zr–X metallic fuel von Ryu, Ho Jin, Lee, Byoung Oon, Oh, Seok Jin, Kim, Jun Hwan, Lee, Chan Bock

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Preliminary Study on the Fabrication of Particulate Fuel through Pressureless Sintering Process von Lee, Chan Bock, Kim, Kihwan, Lee, Jungwon, Kim, Jong-Hwan

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Metal Fuel Development and Verification for Prototype Generation IV Sodium-Cooled Fast Reactor von Lee, Chan Bock, Cheon, Jin Sik, Kim, Sung Ho, Park, Jeong-Yong, Joo, Hyung-Kook

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Diffusion behavior in an interface between U–10Zr alloy and HT-9 steel von Lee, Chong Tak, Kim, Hun, Kim, Tae Kyu, Lee, Chan Bock

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Fabrication of U-10 wt.%Zr Metallic Fuel Rodlets for Irradiation Test in BOR-60 Fast Reactor von Lee, Ho-Jin, Lee, Jungwon, Oh, Seok-Jin, Kim, Jong-Hwan, Kim, Kihwan, Lee, Chan Bock

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FCCI barrier performance of electroplated Cr for metallic fuel von Yang, Seong Woo, Ryu, Ho Jin, Kim, Jun Hwan, Lee, Byoung Oon, Lee, Chan Bock

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Long-term creep characterization of Gr. 91 steel by modified creep constitutive equations von Kim, Woo-Gon, Kim, Sung-Ho, Lee, Chan-Bock

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Characterization of ceramic plasma-sprayed coatings, and interaction studies between U–Zr fuel and ceramic coated interface at an elevated temperature von Kim, Ki Hwan, Lee, Chong Tak, Lee, Chan Bock, Fielding, R.S., Kennedy, J.R.

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Measurement of microstructure and eutectic penetration rate on irradiated metallic fuel after high-temperature heating test von Kim, June-Hyung, Cheon, Jin-Sik, Lee, Byoung-Oon, Kim, Jun-Hwan, Kim, Hee-Moon, Yoo, Boung-Ok, Jung, Yang-Hong, Ahn, Sang-Bok, Lee, Chan-Bock

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Design Concept of Advanced Sodium-Cooled Fast Reactor and Related R D in Korea von Yeong-il Kim, Yong Bum Lee, Chan Bock Lee, Jinwook Chang, Chiwoong Choi

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Interaction between multi-component lanthanide alloy and ferritic-martensitic steel von Kim, Jun Hwan, Cheon, Jin Sik, Kim, June Hyung, Lee, Byoung Oon, Lee, Chan Bock

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Performance of a diffusion barrier under a fuel–clad chemical interaction (FCCI) von Kim, Jun Hwan, Ryu, Ho Jin, Baek, Jong Hyuk, Oh, Seok Jin, Lee, Byoung Oon, Lee, Chan Bock, Yoon, Young Soo

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Design Concept of Advanced Sodium-Cooled Fast Reactor and Related R&D in Korea von Chang, Jinwook, Lee, Yong Bum, Lee, Chan Bock, Choi, Chiwoong, Kim, Yeong-il

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Results of High-Temperature Heating Test for Irradiated U-10Zr(-5Ce) with T92 Cladding Fuel von Kim, June-Hyung, Cheon, Jin-Sik, Lee, Byoung-Oon, Kim, Jun-Hwan, Kim, Hee-Moon, Yoo, Boung-Ok, Jung, Yang-Hong, Ahn, Sang-Bok, Lee, Chan-Bock

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