STATUS OF PYROPROCESSING TECHNOLOGY DEVELOPMENT IN KOREA von Song, Kee-Chan, Lee, Han-Soo, Hur, Jin-Mok, Kim, Jeong-Guk, Ahn, Do-Hee, Cho, Yung-Zun

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Precipitation Characteristics of Uranyl Ions at Different pHs Depending on the Presence of Carbonate Ions and Hydrogen Peroxide von Kim, Kwang-Wook, Kim, Yeon-Hwa, Lee, Se-Yoon, Lee, Jae-Won, Joe, Kih-Soo, Lee, Eil-Hee, Kim, Jong-Seung, Song, Kyuseok, Song, Kee-Chan

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Fabrication of UO2 Porous Pellets on a Scale of 30 kg-U/Batch at the PRIDE Facility von Song, Kee-Chan, Cho, Yung-Zun, Lee, Kwang-Yun, Kang, Sang-Jun, Lee, Ju-Ho, Lee, Jae-Won, Jeon, Sang-Chae, Ahn, Do-Hee

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Electrolytic dissolution characteristics of SIMFUEL in carbonate solutions of high concentration von Kim, Kwang-Wook, Hyun, Jun-Taek, Sung, Sae-Reum, Lee, Eil-Hee, Lee, Kune-Woo, Song, Kee-Chan

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Effects of the different conditions of uranyl and hydrogen peroxide solutions on the behavior of the uranium peroxide precipitation von Kim, Kwang-Wook, Hyun, Jun-Taek, Lee, Keun-Young, Lee, Eil-Hee, Lee, Kune-Woo, Song, Kee-Chan, Moon, Jei-Kwon

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Corrosion behaviour of Y2O3-ZrO2 coatings on IN713LC in a LiCl-Li2O molten salt von CHO, Soo-Haeng, PARK, Byung-Heong, HUR, Jin-Mok, LEE, Han-Soo, SONG, Kee-Chan, LEE, Jong-Hyeon

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Recovery of uranium from (U,Gd)O2 nuclear fuel scrap using dissolution and precipitation in carbonate media von KIM, Kwang-Wook, HYUN, Jun-Taek, LEE, Eil-Hee, PARK, Geun-Il, LEE, Kune-Woo, YOO, Myung-June, SONG, Kee-Chan, MOON, Jei-Kwon

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Study on Electrolytic Recoveries of Carbonate Salt and Uranium from a Uranyl Peroxo Carbonato Complex Solution Generated from a Carbonate-Leaching Process von Kim, Kwang-Wook, Kim, Yeon-Hwa, Lee, Se-Yoon, Lee, Eil-Hee, Song, Kee-Chan, Song, Kyuseok

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Remote fabrication and irradiation test of recycled nuclear fuel prepared by the oxidation and reduction of spent oxide fuel von Jin Ryu, Ho, Chan Song, Kee, Il Park, Geun, Won Lee, Jung, Seung Yang, Myung

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DESIGN OF LSDS FOR ISOTOPIC FISSILE ASSAY IN SPENT FUEL von LEE, YONGDEOK, PARK, CHANG JE, KIM, HO-DONG, SONG, KEE CHAN

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Preparation of uranium oxide powder for nuclear fuel pellet fabrication with uranium peroxide recovered from uranium oxide scraps by using a carbonate–hydrogen peroxide solution von Kim, Kwang-Wook, Lee, Jae-Won, Chung, Dong-Young, Lee, Eil-Hee, Kang, Kweon-Ho, Lee, Kune-Woo, Song, Kee-Chan, Yoo, Myung-June, Park, Geun-Il, Moon, Jei-Kwon

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Continuous electrolytic decarbonation and recovery of a carbonate salt solution from a metal-contaminated carbonate solution von Kim, Kwang-Wook, Kim, Yeon-Hwa, Lee, Se-Yoon, Lee, Eil-Hee, Song, Kyusuk, Song, Kee-Chan

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Uncertainty assessment for the thermal expansion of simulated fuel via the Monte Carlo method von Park, Chang Je, Kang, Kweon Ho, Song, Kee Chan, Yang, Myung Seung

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Uncertainty evaluation of the thermal expansion of simulated fuel von Park, Chang Je, Kang, Kweon Ho, Song, Kee Chan

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EFFECT OF IMPURITIES ON THE MICROSTRUCTURE OF DUPIC FUEL PELLETS USING THE SIMFUEL TECHNIQUE von Park, Geun-Il, Lee, Jae-Won, Lee, Jung-Won, Lee, Young-Woo, Song, Kee-Chan

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Mitigation of Radiation Load by Trapping of Tritium in Off-gas during Dry-processes von Jung, In-Ha, Chun, Joung-Ick, Park, Jang-Jin, Song, Kee-Chan, Yang, Myung-Seung

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Thermal expansion of UO2 and simulated DUPIC fuel von Ho Kang, Kweon, Jin Ryu, Ho, Chan Song, Kee, Seung Yang, Myung

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Characterization of irradiated simulated DUPIC fuel von Jung, In-Ha, Song, Kee-Chan, Kang, Kweon-Ho, Yoo, Byoung-Ok, Jung, Yang-Hong, Park, Hyun-Soo, Yang, Myung-Seung

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EVALUATION OF PROLIFERATION RESISTANCE USING THE INPRO METHODOLOGY von Yang, Myung-Seung, Park, Joo-Hwan, Ko, Won-Il, Song, Kee-Chan, Choi, Kun-Mo, Kim, Jin-Kyoung

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Recovery of uranium from (U,Gd)O 2 nuclear fuel scrap using dissolution and precipitation in carbonate media von Kim, Kwang-Wook, Hyun, Jun-Taek, Lee, Eil-Hee, Park, Geun-Il, Lee, Kune-Woo, Yoo, Myung-June, Song, Kee-Chan, Moon, Jei-Kwon

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