Search Results - "Eom, Hyeon Jin"
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Melting and draining tests on glass waste form for the immobilization of Cs, Sr, and rare-earth nuclides using a cold-crucible induction melting system
Published in Nuclear engineering and technology (2022)“…Cold-crucible induction melting (CCIM) technology has been intensively studied as an advanced vitrification process for the immobilization of highly…”
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Evaluation of physicochemical characteristics and centerline temperatures of Sr ceramic waste form
Published in Heliyon (01-07-2023)“…When disposing of spent fuel, nuclides such as Cs-137 and Sr-90, which generate short-term decay heat, must be removed from the spent nuclear fuel for…”
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Characterization of Waste Generated from Nuclide Management Process in Waste Burden Minimization Technology for Spent Nuclear Fuel
Published in Science and technology of nuclear installations (30-07-2022)“…To reduce the environmental burden caused by the disposal of spent nuclear fuel, waste burden minimization technology is currently being developed at the Korea…”
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Melting and draining tests on glass waste form for the immobilization of Cs, Sr, and rare-earth nuclides using a cold-crucible induction melting system
Published in Nuclear engineering and technology (01-04-2022)“…Cold-crucible induction melting (CCIM) technology has been intensively studied as an advanced vitrification process for the immobilization of highly…”
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5
Electrochemical oxidation of sodium dodecylbenzenesulfonate in Pt anodes with Y2O3 particles
Published in Nuclear engineering and technology (01-12-2022)“…The electrochemical oxidation process has been widely studied in the field of wastewater treatment for the decomposition of organic materials through oxidation…”
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Long-term stability of upgraded SiO2-Al2O3-P2O5 waste form in domestic groundwater for application in radioactive salt waste disposal
Published in Journal of nuclear materials (15-08-2023)“…[Display omitted]…”
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Preparation of silver vanadate glass containing PbO or TeO2 for radioactive iodine immobilization
Published in Progress in nuclear energy (New series) (01-08-2022)Get full text
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Effects of M2O3 (M = Bi, Al) on silver vanadate glass for radioactive iodine immobilization
Published in Annals of nuclear energy (01-07-2021)“…•Silver vanadate glass system was investigated to vitrify radioactive iodine waste.•The loading of iodine in the matrix was approximately 30–36% by weight.•The…”
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Separation and purification of Sr-90 nuclide from a waste mixture
Published in Journal of radioanalytical and nuclear chemistry (2022)“…Sr-90 is utilized as a raw material in various fields such as nuclear batteries, medical applications, and industrial use as a beta particle source. Therefore,…”
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