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POSTECH

Um Wooyong Professor

Education

  • 1995.08 ~ 2001.05 UNIV. OF NEVADA. RENO (박사-수리지구화학)
  • 1990.03 ~ 1994.02 연세대학교 (석사-지구물리학)
  • 1986.03 ~ 1990.02 연세대학교 (학사-)

Career

  • 2010.12 ~ 2017.02 포항공과대학교 첨단원자력공학부
  • 2004.06 ~ 2017.02 WASHINGTON STATE UNIVERSITY ENVIRONMENTAL SCIENCES
  • 2002.03 ~ 2017.02 PACIFIC NORTHWEST NATIONAL LABORATORY ENERGY AND ENVIRONMENTAL DIRECTORATE

Profession

Journal Papers

International
  • Functionalization of layered double hydroxides on bentonite for cesium and iodine retention in highlevel radioactive waste disposal, Chemosphere, , 370, - (2025 )
  • Development of a sulfidized zerovalent irongeopolymer composite for the reductive immobilization of ReOsub4 sub, Journal of Environmental Management, , 373, - (2025 )
  • Monte Carlo Study of an ElectronBased Neutron Source for Bragg Edge Imaging, Nuclear Science and Engineering, , 198, 461-475 (2024 )
  • Low level radioactive waste treatment by coagulation flocculation technique a review, Journal of Radioanalytical and Nuclear Chemistry, , 333, 6079-6091 (2024 )
  • International perspectives on glass waste form development for lowlevel and intermediatelevel radioactive waste, Materials Today, , 80, 594-618 (2024 )
  • Key Progress on Chemistry and Analysis of 238U 99Tc and 137Cs Radionuclides, Korean Journal of Chemical Engineering, , , - (2024 )
  • Assessment of Uranium and Thorium Cocontaminant Exposure from Incidental Concrete Dust Ingestion, Korean Journal of Chemical Engineering, , 41, 2871-2880 (2024 )
  • Engineered Sorbents for Selective Uranium Sequestration from Seawater, ACS EST Water, , 4, 325-345 (2024 )
  • Solubility complexation and thermodynamics of the TcIV–isosaccharinic acid system Trends in the MIV series, Chemosphere, , 364, - (2024 )
  • Application of Clay Materials for Sorption of Radionuclides from Waste Solutions, Minerals, , 13, - (2023 )
  • Design and Application of Materials for Sequestration and Immobilization of sup99supTc, Environmental Science Technology, , , - (2023 )
  • Acute oral toxicity and bioavailability of uranium and thorium in contaminated soil, Nuclear Engineering and Technology, , 55, 1460-1467 (2023 )
  • Tritium separation from radioactive wastewater by hydrogen isotopeselective exchange of hydrogenbonded fluorine, Journal of Industrial and Engineering Chemistry, , 121, 264-274 (2023 )
  • Sorption and mobility of radioactive Ni in Wolsong waste repository site South Korea, APPLIED GEOCHEMISTRY, , 158, - (2023 )
  • Effect of SiAl molar ratio and curing temperatures on the immobilization of radioactive borate waste in metakaolinbased geopolymer waste form, Journal of Hazardous Materials, , 458, - (2023 )
  • Evaluating the impact of drying on leaching from a solidifiedstabilized waste using a monolithic diffusion model, Waste Management, , 165, 27-39 (2023 )
  • Influence of MnO and ZnO on molybdate crystallization in borosilicate glass, Journal of Nuclear Materials, , 576, - (2023 )
  • Recent advances in Fentonlike treatment of radioactive ion exchange resins, Chemical Engineering Journal Advances, , 14, - (2023 )
  • Microstructure and texture analysis of 304 austenitic stainless steel using Bragg edge transmission imaging, Journal of Applied Crystallography, , 56, 1403-1415 (2023 )
  • Waste acceptance criteria testings of a phosphatebased geopolymer waste form to immobilize radioactive borate waste, Journal of Nuclear Materials, , 586, 154671- (2023 )
  • Estimation of radionuclides leaching characteristics in different sized geopolymer waste forms with simulated spent ionexchange resin, Nuclear Engineering and Technology, , 55, 3617-3627 (2023 )
  • Potential of indigenous bacteria driven UVI reduction under relevant deep geological repository DGR conditions, Environmental Pollution, , 329, - (2023 )
  • Dissolution behaviors of PuO2cr in natural waters, Frontiers in Nuclear Engineering, , 2, - (2023 )
  • Technetium TcRhenium Re Solubility and Leaching Behavior from Waste Forms An Overview, Frontiers in Nuclear Engineering, , 1, - (2023 )
  • Decontamination of neutronactivated radioactive concrete waste by separating Eu Co Fe and Mncontaining sand particles using dense medium separation, Journal of Hazardous Materials, , 443, - (2023 )
  • Prediction of stable radon fluoride molecules and geometry optimization using firstprinciples calculations, Scientific Reports, , 13, - (2023 )
  • Stability of SrCO3 within composite Portlandslag cement blends, Cement and Concrete Composites, , 135, - (2023 )
  • Assessment of sulfidated nanoscale zerovalent iron for insitu remediation of cadmiumcontaminated acidic groundwater at a zinc smelter, Journal of Hazardous Materials, , 441, 129915- (2023 )
  • Co2PMS based sulfateradical treatment for effective mineralization of spent ion exchange resin, Chemosphere, , 287, - (2022 )
  • Metallic technetium sequestration in nickel coreshell microstructure during FeOH2 transformation with Ni doping, Journal of Hazardous Materials, , 425, - (2022 )
  • Removal of iodine I and IO3 from aqueous solutions using CoAl and NiAl layered double hydroxides, CHEMICAL ENGINEERING JOURNAL, , 430, - (2022 )
  • Decontamination of radioactive metal wastes using underwater microwave plasma, Journal of Environmental Chemical Engineering, , 10, - (2022 )
  • Partitioning effects and corrosion characteristics of oxyapatite glassceramic wasteforms sequestering rareearth elements, Nuclear Engineering and Technology, , 54, 997-1002 (2022 )
  • Efficient mercury sequestration from wastewaters using palm kernel and coconut shell derived biochars, Environmental Advances, , 8, - (2022 )
  • The evolution of hydrated limebased cementitious waste forms during leach testing leading to enhanced technetium retention, JOURNAL OF HAZARDOUS MATERIALS, , 430, - (2022 )
  • Safety Assessment for the Landfill Disposal of Decommissioning Waste Solidified by Magnesium Potassium Phosphate Cement, Journal of Nuclear Fuel Cycle and Waste Technology, , 20, 13-22 (2022 )
  • Surface Modification of Bentonite for the Improvement of Radionuclide Sorption, Journal of Nuclear Fuel Cycle and Waste Technology, , 20, 1-12 (2022 )
  • Comparative study of PMS oxidation with Fenton oxidation as an advanced oxidation process for CoEDTA decomplexation, Chemosphere, , 300, - (2022 )
  • Kinetics and mechanism of rheniumethylenediaminetetraacetic acid ReIVEDTA complex degradation For 99TcEDTA degradation in the natural environment, Environmental Technology and Innovation, , 27, - (2022 )
  • Simultaneous removal of cesium and iodate using prussian blue functionalized CoCr layered double hydroxide PBLDH, Journal of Environmental Chemical Engineering, , 10, - (2022 )
  • Heat economic and multipath safety HEMPS management on cogeneration of hydrogen and sulfuric acid through modified sulfuriodine cycle, Journal of Environmental Chemical Engineering, , 10, - (2022 )
  • Recycle Glass Waste as a Host for Solidification of Oil Sludge Sisa Kaca Kitar Semula sebagai Perumah untuk Pemejalan Enap Cemar Minyak, Sains Malaysiana, , 51, 1245-1259 (2022 )
  • Immobilization mechanism of radioactive borate waste in phosphatebased geopolymer waste forms, Cement and Concrete Research, , 161, - (2022 )
  • Fentonlike treatment for reduction of simulated carbon14 spent resin, Journal of Environmental Chemical Engineering, , 9, - (2021 )
  • The bioleaching assessment for nuclear power plantsoil contaminated with Co and Cs using AThiooxidans sp, Journal of Environmental Chemical Engineering, , 9, - (2021 )
  • Effect of ion exchange resin particle size on homogeneity and leachability of Cs and Co in polymer waste form, RSC ADVANCES, , 11, 2729-2732 (2021 )
  • Energy safety and absorption efficiency evaluation of a pilotscale H2S abatement process using MDEA solution in a cokeoven gas, JOURNAL OF ENVIRONMENTAL CHEMICAL ENGINEERING, , 9, - (2021 )
  • Efficient radon removal using fluorinefunctionalized natural zeolite, Journal of Environmental Radioactivity, , 233, 106607- (2021 )
  • Evaluating thermal stability of rareearth containing wasteforms at extraordinary nuclear disposal conditions, NUCLEAR ENGINEERING AND TECHNOLOGY, , 53, 2576-2581 (2021 )
  • Development of a Geochemical Speciation Model for Use in Evaluating Leaching from a Cementitious Radioactive Waste Form, ENVIRONMENTAL SCIENCE amp TECHNOLOGY, , 55, 8642-8653 (2021 )
  • Characterization of phosphorylated natural rubber as thorium bioadsorbent prepared by radiationinduced graft polymerization, Radiation Physics and Chemistry, , 187, - (2021 )
  • TopDown Synthesis of NaP Zeolite from Natural Zeolite for the Higher Removal Efficiency of Cs Sr and Ni, Minerals, , 11, 1-15 (2021 )
  • A Focused Ion BeamScanning Transmission Electron Microscopy with EnergyDispersive Xray Spectroscopy Study on Technetium Incorporation within Iron Oxides through FeOH2s Mineral Transformation, ACS EARTH AND SPACE CHEMISTRY, , 5, 525-534 (2021 )
  • Development of geopolymer waste form for immobilization of radioactive borate waste, Journal of Hazardous Materials, , 419, - (2021 )
  • Fenton and Fentonlike wet oxidation for degradation and destruction of organic radioactive wastes, npj Materials Degradation, , 5, - (2021 )
  • Sorption of beryllium in cementitious systems relevant for nuclear waste disposal Quantitative description and mechanistic understanding, Chemosphere, , 282, - (2021 )
  • Uptake of beIi by cement in degradation stage i Wetchemistry and molecular dynamics studies, Minerals, , 11, - (2021 )
  • Chemical and Mechanical Sustainability of Silver Tellurite Glass Containing Radioactive Iodine129, Journal of Nuclear Fuel Cycle and Waste Technology, , 19, 323-330 (2021 )
  • Economicenergyexergyrisk 3ER assessment of novel integrated ammonia synthesis process and modified sulfuriodine cycle for coproduction of ammonia and sulfuric acid, Korean Journal of Chemical Engineering, , 38, 2381-2396 (2021 )
  • Magnesium potassium phosphate cements to immobilize radioactive concrete wastes generated by decommissioning of nuclear power plants, Nuclear Engineering and Technology, , 53, 2261-2267 (2021 )
  • Process optimization and safety assessment on a pilotscale Bunsen process in sulfur–iodine cycle, International Journal of Hydrogen Energy, , 46, 33616-33634 (2021 )
  • The comprehensive evaluation of available pilotscale H2S abatement process in a cokeoven gas Efficiency economic energy and environmental safety 4ES, Journal of Environmental Chemical Engineering, , 9, 106903- (2021 )
  • Separation of Light RareEarth Elements Using GasPressurized Extraction Chromatography, Mass Spectrometry Letters, , 12, 186-191 (2021 )
  • Nanostructured MgFe and CoCr layered double hydroxides for removal and sequestration of iodine anions, CHEMICAL ENGINEERING JOURNAL, , 380, - (2020 )
  • Impact of Cr and Co on Tc99 retention in magnetite A combined study of ab initio molecular dynamics and experiments, JOURNAL OF HAZARDOUS MATERIALS, , 387, - (2020 )
  • Kinetics of CoMingled Tc99 and Cr Removal during Mineral Transformation of Ferrous Hydroxide, ACS EARTH AND SPACE CHEMISTRY, , 4, 218-228 (2020 )
  • Dissolved Carbonate and pH Control the Dissolution of Uranyl Phosphate Minerals in FlowThrough Porous Media, ENVIRONMENTAL SCIENCE amp TECHNOLOGY, , 54, 6031-6042 (2020 )
  • Relationship between leaching behavior and glass structure of calciumaluminoborate waste glasses with various La2O3 contents, JOURNAL OF NUCLEAR MATERIALS, , 539, - (2020 )
  • Decontamination of concrete waste from nuclear power plant decommissioning in South Korea, ANNALS OF NUCLEAR ENERGY, , 149, - (2020 )
  • Charge transfer rhenium complexes analogue to pertechnetate removal, Journal of Environmental Chemical Engineering, , 8, - (2020 )
  • Transport of Colloidal Particles in Microscopic Porous Medium Analogues with Surface Charge Heterogeneity Experiments and the Fundamental Role of SingleBead Deposition, ENVIRONMENTAL SCIENCE TECHNOLOGY, , 54, 13651-13660 (2020 )
  • Waterdispersible nanocolloids and higher temperatures promote the release of carbon from riparian soil, Vadose Zone Journal, , 19, - (2020 )
  • Comparative Study Between Geopolymer and Cement Waste Forms for Solidification of Corrosive Sludge, Journal of Nuclear Fuel Cycle and Waste Technology, , 18, 465-479 (2020 )
  • Tc99 immobilization from offgas waste streams using nickeldoped iron spinel, JOURNAL OF HAZARDOUS MATERIALS, , 364, 69-77 (2019 )
  • Development of bismuthfunctionalized graphene oxide to remove radioactive iodine, DALTON TRANSACTIONS, , 48, 478-485 (2019 )
  • Insights into the physical and chemical properties of a cementpolymer composite developed for geothermal wellbore applications, CEMENT CONCRETE COMPOSITES, , 97, 279-287 (2019 )
  • Investigation of H3 Tc99 and Sr90 transport in fractured rock and the effects of fracturefillingcoating material at LILW disposal facility, ENVIRONMENTAL GEOCHEMISTRY AND HEALTH, , 41, 411-425 (2019 )
  • Relative permeability for water and gas through fractures in cement, PLOS ONE, , 14, - (2019 )
  • Development of metakaolinbased geopolymer for solidification of sulfaterich HyBRID sludge waste, Journal of Nuclear Materials, , 518, 247-255 (2019 )
  • Temporal changes of geochemistry and microbial community in low and intermediate level waste LILW repository South Korea, Annals of Nuclear Energy, , 128, 309-317 (2019 )
  • Effect of seawater intrusion on radioactive strontium 90Sr sorption and transport at nuclear power plants, RADIOCHIMICA ACTA, , 106, 1-86 (2018 )
  • Magnetitebased adsorbents for sequestration of radionuclides a review, Royal Society of Chemistry Advances, , 8, 2521-2540 (2018 )
  • Uranium speciation in acid wasteweathered sediments The role of aging and phosphate amendments, APPLIED GEOCHEMISTRY, , 89, 109-120 (2018 )
  • Removal of Chalk River unidentified deposit CRUD radioactive waste by enhanced electrokinetic process, JOURNAL OF INDUSTRIAL AND ENGINEERING CHEMISTRY, , 57, 89-96 (2018 )
  • Effect of Technetium99 sources on its retention in low activity waste glass, JOURNAL OF NUCLEAR MATERIALS, , 503, 235-244 (2018 )
  • Synthesis of rheniumdoped tin dioxide for technetium radioactive waste immobilization, JOURNAL OF NUCLEAR MATERIALS, , 505, 134-142 (2018 )
  • Study of Mobility for Radionuclides in Nuclear Facility Sites, 자원환경지질, , 51, 99-111 (2018 )
  • Characterizing Technetium in Subsurface Sediments for Contaminant Remediation, ACS EARTH AND SPACE CHEMISTRY, , 2, 1145-1160 (2018 )
  • CrVI Effect on Tc99 Removal from Hanford LowActivity Waste Simulant by Ferrous Hydroxide , ENVIRONMENTAL SCIENCE TECHNOLOGY, , 52, 11752-11759 (2018 )
  • Effect of chemical and physical heterogeneities on colloidfacilitated cesium transport, JOURNAL OF CONTAMINANT HYDROLOGY, , 213, 22-27 (2018 )
  • Dissolution of studtite UO2O2H2O4 in various geochemical conditions, JOURNAL OF ENVIRONMENTAL RADIOACTIVITY, , 189, 57-66 (2018 )
  • Bioaccessibility assessment of232TH and238U from lanthanide concentrate and water leach purification residue in malaysia Penilaian biokebolehcapaian bagi232Th dan238U dalam lantanida pekat dan residu permurnian larut resap air di malaysia, Malaysian Journal of Analytical Sciences, , 22, 794-806 (2018 )
  • Structure analysis of vitusite glassceramic waste forms using extended Xray absorption fine structures, Ceramics International, , 43, 4687-4691 (2017 )
  • Rates and mechanisms of uranyl oxyhydroxide mineral dissolution, Geochimica et Cosmochimica Acta, , 207, 298-321 (2017 )
  • Synthesis of Tributyl PhosphateCoated Hydroxyapatite for Selective Uranium Removal, Industrial Engineering Chemistry Research, , 56, 3399-3406 (2017 )
  • Reduction and Simultaneous Removal of 99Tc and Cr by FeOH2s Mineral Transformation, ENVIRONMENTAL SCIENCE AND TECHNOLOGY, , 51, 8635-8642 (2017 )
  • Effects of hydrated lime on radionuclides stabilization of Hanford tank residual waste, CHEMOSPHERE, , 185, 171-177 (2017 )
  • Tellurite glasses for vitrification of technetium99 from pyrochemical processing, JOURNAL OF NUCLEAR MATERIALS, , 493, 1-5 (2017 )
  • PolymerCement Composites with SelfHealing Ability for Geothermal and Fossil Energy Applications, CHEMISTRY OF MATERIALS, , 29, 4708-4718 (2017 )
  • Superparamagnetic Adsorbent Based on Phosphonate Grafted Mesoporous Carbon for Uranium Removal, INDUSTRIAL ENGINEERING CHEMISTRY RESEARCH, , 56, 9821-9830 (2017 )
  • Uranium Release from Acidic Weathered Hanford Sediments SinglePass FlowThrough and Column Experiments, ENVIRONMENTAL SCIENCE TECHNOLOGY, , 51, 11011-11019 (2017 )
  • Enhanced 99Tc retention in glass waste form using TcIVincorporated Fe minerals, JOURNAL OF NUCLEAR MATERIALS, , 495, 455-462 (2017 )
  • Recyclable superparamagnetic adsorbent based on mesoporous carbon for sequestration of radioactive Cesium, Chemical Engineering Journal, , 308, 798-808 (2017 )
  • Removal mechanism for technetium 99Tc using FeOH2s at the Hanford Site WA USA, ABSTRACTS OF PAPERS OF THE AMERICAN CHEMICAL SOCIETY, , 253, - (2017 )
  • Synthesis of tributyl phosphate TBPcoated apatite for uranium removal, ABSTRACTS OF PAPERS OF THE AMERICAN CHEMICAL SOCIETY, , 252, - (2016 )
  • Numerical Simulation of Permeability Change in Wellbore Cement Fractures after Geomechanical Stress and Geochemical Reactions Using Xray Computed Tomography Imaging, ENVIRONMENTAL SCIENCE TECHNOLOGY, , 50, 6180-6188 (2016 )
  • Impeding Tc99IV mobility in novel waste forms, Nature Communications, , 7, - (2016 )
  • Computational Investigation of TechnetiumIV Incorporation into Inverse Spinels Magnetite Fe3O4 and Trevorite NiFe2O4, ENVIRONMENTAL SCIENCE TECHNOLOGY, , 50, 5216-5224 (2016 )
  • Synthesis of phosphate modified magnetic mesoporous carbon for removal of uranium, ABSTRACTS OF PAPERS OF THE AMERICAN CHEMICAL SOCIETY, , 251, - (2016 )
  • Reductive capacity measurement of waste forms for secondary radioactive wastes, JOURNAL OF NUCLEAR MATERIALS, , 467, 251-259 (2015 )
  • Benchscale electrokinetic remediation for cesiumcontaminated sediment at the Hanford Site USA, JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY, , 304, 615-625 (2015 )
  • Sludge Reduction by H2O2 Oxidation with FeMgO Catalyst, WATER ENVIRONMENT RESEARCH, , 87, 675-682 (2015 )
  • Biogeochemical changes at early stage after the closure of radioactive waste geological repository in South Korea, ANNALS OF NUCLEAR ENERGY, , 71, 6-10 (2014 )
  • Effects of iron oxides on the rheological properties of cementitious slurry, COLLOIDS AND SURFACES APHYSICOCHEMICAL AND ENGINEERING ASPECTS, , 453, 94-100 (2014 )
Domestic Journal Papers
  • 불포화 암반 파쇄대를 통한 핵종 이동, 대한환경공학회지, , 37, 465-471 (2015 )
General Journal Journal
  • Inorganic Waste Forms for Efficient Immobilization of Radionuclides, Acs Environmental Science and Technology Engineering, , 1, 1149-1170 (2021 )

Conference Proceedings

  • Efficient Inorganic 14C Removal using Ettringite from Waste Solution, , 0, 0, - (2024)
  • Homogeneity Evaluation of Geopolymer Waste Form Containing Radioactive Spent Ion Resins Using LIBS and Statistical Approach, , 0, 0, - (2023)
  • Effect of Polycarboxylicester PCE Cement Admixture on Radionuclide Release in Repository Environments, , 0, 0, - (2023)
  • Solidification of Radioactively Contaminated Soils Using Cement Waste Forms, , 0, 0, - (2023)
  • The Effect of Isosaccharinic acid ISA on the Solubility of RheniumIV Oxide, , 0, 0, - (2022)
  • Release of Sr from SrCoprecipitated Calcite Under Various Environment Conditions, , 0, 0, - (2022)
  • The Effect of ISA on the Sorption and the Solubility of Nicke, , 0, 0, - (2022)
  • Solubility Experiment for the Potential role of Concrete Admixture on the Radionuclide Mobility, , 0, 0, - (2022)
  • Removal of Aqueous Uranium by Indigenous Bacteria Under Conditions Relevant for Deep Geological Repository of Nuclear Waste, , 0, 0, - (2022)
  • Synthesis Characterization and Application of Ettringite for Sequestration of 14C from Simulated Waste Solution, Synthesis Characterization and Application of Ettringite for Sequestration of 14C from Simulated Waste Solution, 0, 0, - (2022)
  • Decontamination of Radioactive Wastes Using Underwater Microwave Plasma, , 0, 0, - (2021)
  • Decontamination of NeutronActivated Concrete Waste by Dense Medium Separation, , 0, 0, - (2021)
  • Theoretical Study on the Reaction of Xenon and Fluorine From DFT Calculation, , 0, 0, - (2021)
  • Bioaccessibility and Absolute Bioavailability of Uranium and Thorium in IAEA312 by in Vitro and In Vivo Bioassays, , 0, 0, - (2021)
  • Solidification of Spent Ionexchange Resin Using Metakaolinbased Geopolymer Waste Form, , 0, 0, - (2021)
  • Effect of Humic Acid on Iodine Speciation and Removal Using Layered Double Hydroxides, , 0, 0, - (2021)
  • A Hybrid Advance Oxidation Process for Effective Treatment of Spent Resin, , 0, 0, - (2021)
  • Enhanced Iodine Sorption by Layered Double Hydroxides Modified Bentonite, , 0, 0, - (2021)
  • Study for Iodine Removal Mechanism Using CoAl and NiAl Layered Double Hydroxides Under Aqueous Condition, , 0, 0, - (2021)
  • Inorganic Surface Modification of Bentonite to Increase Radionuclide Removal, , 0, 0, - (2021)
  • Structural Evolution of PhosphateBased Geopolymer Waste Forms Containing Radioactive Borate Waste, , 0, 0, - (2021)

IP

  • 엄우용,김병관, 인산 기반의 지오폴리머 원료를 활용한 방사성 폐이온교환수지 고화방법 및 이에 따른 방사성 폐이온교환수지 고화체, -, PCT/KR2024/0144 (P202)
  • 김병관,엄우용,김주은, 인산 기반의 지오폴리머 원료를 활용한 방사성 요오드 고화방법 및 이에 따른 방사성 요오 드 고화체, 한국, 10-2024-0148270 (IP24)
  • 엄우용,김병관,마현민, 인산 기반의 지오폴리머 원료를 활용한 방사성 산성폐액 고화방법 및 이에 따른 방사성 산성폐액 고화체, 한국, 10-2024-0096445 (IP24)
  • 엄우용,김병관,마현민, 메타카올린 기반의 알칼리 지오폴리머 원료를 활용한 방사성 농축폐액 분말 고화방법 및 이 에 따른 방사성 농축폐액 분말 고화체, 한국, 10-2024-0096413 (IP24)
  • 엄우용,김병관, 인산 기반의 지오폴리머 원료를 활용한 방사성 농축폐액 분말 고화방법 및 이에 따른 방사 성 농축폐액 분말 고화체, 한국, 10-2024-0096385 (IP24)
  • 엄우용,김병관, 인산 기반의 지오폴리머 원료를 활용한 방사성 폐이온교환수지 고화방법 및 이에 따른 방사 성 폐이온교환수지 고화체, 한국, 10-2024-0096340 (IP24)
  • 엄우용,강재은,Singh Bhupendra Kumar, 라돈 제거용 흡착제, 이의 제조방법 및 이를 이용한 라돈 제거방법, USA, 18/025,001 (2023)
  • 엄우용,강재혁,김병관,이주혁, 붕소가 포함된 방사성 폐기물 고화방법 및 이에 따른 방사성 폐기물 고화체, USA, 18/024,827 (2023)
  • 엄우용,김효주, 수소 동위원소에 대한 차별적 결합 특성을 갖는 수소 동위원소 흡착제, 이의 제조방법 및 이를 이용한 수소 동위원소 분리방법, USA, 18/089,004 (2022)
  • 엄우용,김효주, 수소 동위원소에 대한 차별적 결합 특성을 갖는 수소 동위원소 흡착제, 이의 제조방법 및 이를 이용한 수소 동위원소 분리방법, USA, 18/089,004 (2022)
  • 엄우용,김주은,홍석주, 층상이중수산화물로 개질된 벤토나이트로 구성된 완충재 및 이의 제조방법, USA, 18/066,456 (2022)
  • 엄우용,양석훈, EGME와 동결-해동 과정을 이용한 세슘으로 오염된 점토광물에서의 세슘 제거방법, 한국, 10-2022-0096573 (2022)
  • 엄우용,김주은,홍석주, 층상이중수산화물로 개질된 벤토나이트로 구성된 완충재 및 이의 제조방법, 한국, 10-2022-0064675 (2022)
  • 엄우용,김효주, 수소 동위원소에 대한 차별적 결합 특성을 갖는 수소 동위원소 흡착제, 이의 제조방법 및 이를 이용한 수소 동위원소 분리방법, USA, 17/592,799 (2021)
  • 엄우용,김효주, 수소 동위원소에 대한 차별적 결합 특성을 갖는 수소 동위원소 흡착제, 이의 제조방법 및 이를 이용한 수소 동위원소 분리방법, USA, 17/592,799 (2021)
  • 엄우용,홍석주,남성식, 모의 표면오염 콘크리트 시료 제조방법, 한국, 10-2021-0164180 (2021)
  • 엄우용,강재은,Singh Bhupendra Kumar, 라돈 제거용 흡착제, 이의 제조방법 및 이를 이용한 라돈 제거방법, -, PCT/KR2021/0103 (2021)
  • 엄우용,강재혁,김병관,이주혁, 붕소가 포함된 방사성 폐기물 고화방법 및 이에 따른 방사성 폐기물 고화체, -, PCT/KR2021/0083 (2021)
  • 엄우용,김효주, 수소 동위원소에 대한 차별적 결합 특성을 갖는 수소 동위원소 흡착제, 이의 제조방법 및 이를 이용한 수소 동위원소 분리방법, 한국, 10-2021-0096843 (2021)
  • 김효주,엄우용, 수소 동위원소에 대한 차별적 결합 특성을 갖는 수소 동위원소 흡착제, 이의 제조방법 및 이를 이용한 수소 동위원소 분리방법, 한국, 10-2021-0096843 (2021)
  • 엄우용,홍석주, 중액분리법을 이용한 방사화 콘크리트 폐기물에서의 방사성 핵종 분리방법, 한국, 10-2021-0070870 (2021)
  • 엄우용,홍석주, 중액분리법을 이용한 방사화 콘크리트 폐기물에서의 방사성 핵종 분리방법, 한국, 10-2021-0070870 (2021)
  • 엄우용,김병관,강재혁,이주혁, 붕소가 포함된 방사성 폐기물 고화방법 및 이에 따른 방사성 폐기물 고화체, 한국, 10-2021-0076131 (2021)
  • 엄우용,강재은,Singh Bhupendra Kumar, 라돈 제거용 흡착제, 이의 제조방법 및 이를 이용한 라돈 제거방법, 한국, 10-2021-0023307 (2021)
  • 엄우용,이주혁, 방사성코발트와 화학적으로 결합된 EDTA 분해방법 및 이의 분해장치, 한국, 10-2021-0012763 (2020)
  • 엄우용,전준성,홍석주,HAFEEZ MUHAMMAD AAMIR, 펜톤유사공정을 이용한 IRN-150 폐수지 분해방법 및 분해장치, 한국, 10-2021-0002818 (2020)
  • 엄우용,전준성,홍석주,HAFEEZMUHAMMAD AAMIR, 펜톤유사공정을 이용한 IRN-150 폐수지 분해방법 및 분해장치, 한국, 10-2021-0002818 (2020)
  • 엄우용,홍석주, 방사성 세슘의 고정화방법으로서 폴루사이트 합성방법 및 이에 따라 합성된 폴루사이트, 한국, 10-2020-0109148 (2020)
  • 엄우용,홍석주, 방사성 세슘의 고정화방법으로서 폴루사이트 합성방법 및 이에 따라 합성된 폴루사이트, 한국, 10-2020-0109148 (2020)
  • 엄우용,홍석주, 방폐장에서 사용되는 뒷채움재 제조방법, 이에 따른 뒷채움재, 이 를 이용한 방사성 폐기물 처분방법 및 이를 이용한 방폐장, 한국, 10-2020-0122165 (2020)
  • 엄우용,홍석주, 방폐장에서 사용되는 뒷채움재 제조방법, 이에 따른 뒷채움재, 이 를 이용한 방사성 폐기물 처분방법 및 이를 이용한 방폐장, 한국, 10-2020-0122165 (2020)
  • 엄우용,김주은,강재혁, 프러시안 블루로 코팅된 층상이중수산화물로 구성된 방사성물질 흡착제 및 이의 제조방법, 한국, 10-2020-0025835 (2019)
  • 김주은,강재혁,엄우용, 프러시안 블루로 코팅된 층상이중수산화물로 구성된 방사성물질 흡착제 및 이의 제조방법, 한국, 10-2020-0025835 (2019)
  • 허종,전재남,박원지,이호정,이청원,엄우용,조항래,김천우, 붕규산 유리 고화체 및 그 제조방법, 한국, 10-2020-0006757 (2019)
  • 김현주,엄우용, 해수에 포함된 우라늄을 흡착하는 우라늄 흡착제 및 이의 방법, 한국, 10-2019-0064520 (2019)
  • 김현주,엄우용, 우라늄 흡착제 및 이의 제조방법, 한국, 10-2019-0064511 (2019)
  • 엄우용,김천우,조항래,강재혁,박상수,허종, 동결건조 방법을 이용한 Chalcogel 흡착제 합성 방법 개발, 한국, 10-2019-0016001 (2018)
  • 엄우용,김천우,조항래,강재혁,박상수,허종, 동결건조 방법을 이용한 Chalcogel 흡착제 합성 방법 개발, 한국, 10-2019-0016001 (2018)
  • 엄우용,안진모,김선병, 방사성 폐기물 고화방법 및 이에 따른 방사성 폐기물 고화체, 한국, 10-2019-0048946 (2018)
  • 엄우용,안진모,김선병, 방사성 폐기물 고화방법 및 이에 따른 방사성 폐기물 고화체, 한국, 10-2019-0048946 (2018)
  • 김송현,엄우용, 방사성폐기물 고화체 균질도 검사 시스템, 한국, 10-2018-0045336 (2018)
  • 김송현,엄우용, 방사성폐기물 고화체 균질도 검사 시스템, 한국, 10-2018-0045336 (2018)
  • 김원석,한상수,엄우용,이정환,하재철,윤정현, 불포화대에서의 방사성 핵종 이동 특성 실험장치 및 방법, 한국, 10-2017-0125696 (2017)
  • 김원석,한상수,엄우용,이정환,하재철,윤정현, 불포화대에서의 방사성 핵종 이동 특성 실험장치 및 방법, 한국, 10-2017-0125696 (2017)
  • 엄우용,김원석,한상수, 비스무트그래핀산화물을 함유한 요오드 흡착제 및 이를 포함한 고정층 컬럼 및 성형물, 한국, 10-2016-0072811 (2016)
  • 엄우용,김원석,한상수, Bismuth Graphene Oxide 흡착제를 이용한 요오드 제거 기술, 한국, 10-2016-0072811 (2016)
  • 엄우용,김원석,한상수, 비스무트그래핀산화물 제조방법 및 이를 이용한 요오드 흡착방법, 한국, 10-2016-0072812 (2016)
  • 엄우용,김원석,한상수, 방사성 요오드 흡착효율 향상을 위한 Bismuth Graphene Oxide 합성 방법 개발, 한국, 10-2016-0072812 (2016)
  • 한상수,김원석,엄우용, 방사성 요오드 흡착효율 향상을 위한 Bismuth Graphene Oxide 합성 방법 개발, 한국, 10-2016-0072812 (2016)

Invited Talk or Presentations

  • 고준위 방사성폐기물 처분을 위한 LowpH 시멘트 및 지오폴리머 개발 국제 연구 동향, , 0, 0, - (2024)
  • Comparative Effects of Organic and Inorganic Ligands on Uranium Release From Uranophane, , 0, 0, - (2024)
  • Analysis of Domestic and Overseas Distribution Coefficients for Radionuclides Sorption on Buffer Material Under Aerobic Condition, , 0, 0, - (2024)
  • Immobilization of Iodine Using Phosphatebased Geopolymer Waste Forms, , 0, 0, - (2024)
  • New Insights Into the Influence of Calcium on the Immobilization of Radioactive Borate Waste in Metakaolinbased Geopolymer Waste Forms, , 0, 0, - (2024)
  • Effect of JahnTeller Distortion on Iodine Sequestration of CuAl Layered Double Hydroxides, , 0, 0, - (2024)
  • Bioaccessibility of Cs orCo contaminated Media Using in Vitro Assay and Human Biokinetic Modeling, , 0, 0, - (2024)
  • Input Data Construction for Safety Study for 129Iodine on Radioactive Waste Disposal Facility in Korea, , 0, 0, - (2024)
  • Impact of Ba on the Immobilization of Selenate Ettringite in MetakaolinBased Geopolymer Waste Form, Transactions of the American Nuclear Society, 0, 0, 56-58 (2024)
  • Homogeneity Evaluation for Geopolymer Waste Form With Spent Ionexchange Resin, Transactions of the American Nuclear Society, 0, 0, 53-55 (2024)
  • Homogeneity Evaluation Test of Solid Waste Form Containing Spent Ion Exchange Resins Using Statistical Analysis, , 0, 0, - (2024)
  • Effect of SiAl Ratio in Metakaolinbased Geopolymer Formulation on Immobilization of Radioactive Selenium, , 0, 0, - (2024)
  • Evaluation of Diffusion Characteristics of Radionuclides in Buffer Matrix Under Oxidation Conditions, , 0, 0, - (2024)
  • Assessment of Structural Stability and Leaching Characteristics of Phosphatebased Geopolymer Waste Form Containing Radioactive Spent Ion Exchange Resins, , 0, 0, - (2024)
  • Isotope Selective Electrical Transmission of Hydrogen HD in Liquid Electrolyte Through PTFE Reinforced PFSA Polymer Graphene Composite Membrane , , 0, 0, - (2024)
  • Sorption and Diffusion of Nonradioactive Isotopes under Oxidizing Disposal Environments, , 0, 0, - (2024)
  • Comparative Study of Thermodynamic Database TDB for Estimation of Radionuclide Solubility in KURT Conditions, , 0, 0, - (2024)
  • Leaching Behavior of Cesium from Geopolymer Waste Form with Heterogeneously Distributed Spent Ion Exchange Resin, , 0, 0, - (2024)
  • Effect of Organic Ligands on Uranium Release from Uranophane Dissolution, , 0, 0, - (2024)
  • Application of Cebased Metal–Organic Framework MOF for Efficient Uranium Extraction from Seawater UES, , 0, 0, - (2024)
  • Review of Test Methods for the Cation Exchange Capacity of Bentonite Buffer in a HighLevel Waste Repository, , 0, 0, - (2024)
  • Diffusion Properties of Radionuclides on Altered Granitic Rock under Aerobic Condition, , 0, 0, - (2024)
  • A DFT Study of the Radium Adsorption on Bentonite, , 0, 0, - (2024)
  • In Vitro Gastric and Intestinal Bioaccessibility of Cesium from Ingested Contaminated Concrete Waste, , 0, 0, - (2024)
  • Highly Stable and Hierarchical porous Cebased MOF for Efficient Uranium Extraction from Seawater, , 0, 0, - (2024)
  • Ab initio calculations on the stability and geometry of radon fluoride, , 0, 0, - (2023)
  • Estimation of bioaccessibility of uranium and cobalt in contaminated media by in vitro method, , 0, 0, - (2023)
  • Structural insights into radioactive borate waste immobilization in phosphatebased geopolymer waste form, , 0, 0, - (2023)
  • Impact of calcium hydroxide on physical characteristics and leaching stability of metakaolinbased geopolymer waste form containing radioactive borate waste, , 0, 0, - (2023)
  • Strontium90 Immobilization Via Coprecipitation with Respect to Calcite in Various Disposal Site Conditions, , 0, 0, - (2023)
  • The Effect of Isosaccharinic Acid on the Mobility of Nickel in the Near and FarField Repository Conditions, , 0, 0, - (2023)
  • Ca hydroxide가 방사성 붕산염 폐기물을 포함한 메타카올린 기반 지오폴리머 고화체의 구조적 특성에 미치는 영향, , 0, 0, - (2023)
  • Enhanced Anion Sorption Properties of Bentonite by Modifying Layered Double Hydroxides, , 0, 0, - (2023)
  • IsotopeSelective Hydrogen Isotope Exchange for Separation of Tritium from Radioactive Wastewater, , 0, 0, - (2023)
  • Bioaccessibility of uranium and thorium from ingested contaminated soil and concrete in humans, , 0, 0, - (2022)
  • Radiological Evaluation of Uranium and Thorium by due to Contaminated Soil Ingestion A Comparative Study of Annual Committed Effective Dose and Excess Lifetime Cancer Risk, , 0, 0, - (2022)
  • Evaluation of Waste Form Acceptance Criteria for PhosphateBased Geopolymer for Immobilization of Spent Ion Exchange Resins, , 0, 0, - (2022)
  • Enhanced Iodine Removal by Modified Bentonite With Layered Double Hydroxides, , 0, 0, - (2022)
  • Removal of Cesium Form Montmorillonite by Using Ethylene Glycol Monoethyl Ether EGME and FreezingThawing Process, , 0, 0, - (2022)
  • Theoretical Study for Stability and Geometry Optimization of Radon Fluoride Molecules, , 0, 0, - (2022)
  • Bioaccessibilty of 238UContaminated Soil, , 0, 0, - (2022)
  • Measurement for SelfDisposal of Wastes From Radioactive Material Research Facility, , 0, 0, - (2022)
  • The Solubility Measurement of Radionuclides in Simulant Oxidative Groundwater, , 0, 0, - (2022)
  • Development of BentoniteNaPzeolite Buffer Material for Improved Radionuclide Sorption Efficiency, , 0, 0, - (2022)
  • Migration Behavior of Iodine Under the Low and Intermediate Level of Radioactive Waste Repository Conditions in South Korea, , 0, 0, - (2022)
  • Solidification Properties of Magnesium Phosphate Cement for Cesium Strontium and Cobalt, , 0, 0, - (2022)
  • Influence of SiAl Ratio and Curing Temperature of Geopolymer Waste Forms on Immobilization of Radioactive Borate Waste, , 0, 0, - (2022)
  • Effect of Sulfate Radical on Advanced Oxidation Process for Treatment of Liquid Scintillation Waste, , 0, 0, - (2022)
  • Radionuclides Leaching Characteristics in Different Sized Geopolymer Waste Forms with Simulated Spent Ionexchange Resin, , 0, 0, - (2022)
  • Effect of ZnO Content on Crystallization Tendency of Mobearing Borosilicate Glass, , 0, 0, - (2022)
  • Removal of 14C in Aqueous Phase Using Isotope Exchange Reaction, , 0, 0, - (2022)
  • Geochemical Factors Influencing the Radon Content in Groundwater and Application of Sorbent for Radon Removal, , 0, 0, - (2022)
  • Optimization and Evaluation of Geopolymer waste form for Immobilization of Radioactive Spent Ionexchange Resins, , 0, 0, - (2022)
  • 사용후핵연료 장기 심층처분에서 발생 가능한 라돈의 잠재 위험도 및 지하수 환경 내 거동, , 0, 0, - (2021)
  • A Study on the Removal of Tritium in Radioactive Wastewater Using the Chemical Affinity Quantum Sieve Effect of Fluorine, , 0, 0, - (2021)
  • 중액 분리법을 이용한 방사성 콘크리트 폐기물의 제염 기술 개발, , 0, 0, - (2021)
  • Synthesis of Prussian Blue Functionalized CoCr Layered Double Hydroxides to Treat Cesium and Iodate Together, , 0, 0, - (2020)
  • Solidification of borate waste using metakaolinbased geopolymer waste form, , 0, 0, - (2020)
  • Homogeneity Test of Cesium and Cobalt Loaded Ion Exchange Resins in Polymer Waste Form, , 0, 0, - (2020)
  • Mercury II Removal From Aqueous Solution Using Sulfurfunctionalized Biochar, , 0, 0, - (2020)
  • Reduction of Radioactive Concrete Waste Using Dense Medium Separation Technology , , 0, 0, - (2020)
  • Solubility of Tc99 With Various Conditions in the Wolsung Repository Site South Korea, , 0, 0, - (2020)
  • Efficient Decomplexation of CoEDTA Mixed Radioactive Waste by Advanced Oxidation Process, , 0, 0, - (2020)
  • Sulfate Radical Advance Oxidation Process for Degradation of Spent Resin, , 0, 0, - (2020)
  • Hydrothermal synthesis of pollucite below 100 degrees for Cs immobilization, , 0, 0, - (2020)
  • Simultaneous Removal of Both Cesium and Iodate using Prussian Blue Functionalized Layered Double Hydroxides PBLDH, , 0, 0, - (2020)
  • Iodine I and IO3 Sequestration and Removal by CoAl and NiAl Layered Double Hydroxides, , 0, 0, - (2020)
  • Application of Fluorinefunctionalized Zeolite to Increase Radon Removal , , 0, 0, - (2020)
  • FluorineFunctionalized Mesoporous Silica for Selective Removal of Tritium From Nuclear Waste Water, , 0, 0, - (2020)
  • FentonLike Process for Treatment of IRN150 Resin with Simulated 14C, , 0, 0, - (2020)
  • Correlation of Absolute 238U Bioavailability 238UABA and 238U Bioaccessibility Fraction 238UBAF Using IAEA312 Standard Reference Soil, , 0, 0, - (2020)
  • Evaluation of Absolute Oral Bioavailability Of Thorium using Female Sprague Dawley Rats and Comparison with Unified BARGE Bioaccessibility Method in IAEA312 Standard Reference Soil, , 0, 0, - (2019)
  • 원전 해체 제염 폐기물 흡착제 담지용 유리고화체 개발, 원전 해체 제염 폐기물 흡착제 담지용 유리고화체 개발, 0, 0, - (2019)
  • Structural and Compositional Analysis of Biochar produced from Palm Kernel and Coconut Shells in Ghana for Uranium Removal, , 0, 0, - (2019)
  • Synthesis of chalcogenide sorbent for Cs removal, , 0, 0, - (2019)
  • Removal of Cobalt From the Radioactive Concrete Waste Using SinkFloat Separation, , 0, 0, - (2019)
  • Leaching Behavior of Two Waste Glass Forms IodineTellurite and RheniumTellurite under Radioactive Waste Repository Conditions, Leaching Behavior of Two Waste Glass Forms IodineTellurite and RheniumTellurite under Radioactive Waste Repository Conditions, 0, 0, - (2019)
  • Geochemical factors influencing the radon content in groundwater, , 0, 0, - (2019)
  • Development of Cement Waste Form for Decommissioning Wastes of Nuclear Power Plant, , 0, 0, - (2019)
  • Leaching Behaviors of Co Cs and I From Geopolymer and Cement Waste Forms Containing Highsulfate Sludge Waste, , 0, 0, - (2019)
  • Decontamination of radionuclides in wastewater after soilwashing process, , 0, 0, - (2019)
  • Simultaneous Removal of Both Cesium and Iodine using Prussian Blue Functionalized Layered Double Hydroxides PBLDH, , 0, 0, - (2019)
  • Durability and Leaching Behavior of Geopolymer Waste form for HyBRID Sludge Waste, , 0, 0, - (2019)
  • Feasibility Study on Automatic Monitoring System of NaP Zeolite Defect for Increase of Radionuclide Removal Efficiency, , 0, 0, - (2019)
  • Estimation System of 3D Source Location with MultiDetector Responses Using Deep Learning Technique, , 0, 0, - (2019)
  • A new pollucite synthesis method to immobilize the radioactive Cs under the 100℃, , 0, 0, - (2019)
  • FentonFenton like treatment of spent ion exchange resin, , 0, 0, - (2019)
  • Sorption of Beryllium in Fresh Ordinary Portland Cement Paste, , 0, 0, - (2019)
  • Synthesis of Zeolite NaP from Natural Zeolite and Application for Radionuclide Removal, , 0, 0, - (2019)
  • Removal of Radionuclides in Waste Solution using Cancrinite Sorbent, , 0, 0, - (2019)
  • Kinetics of Comingled 99Tc and CrVI Removal from Nuclear Waste Streams Using FeOH2s, , 0, 0, - (2019)
  • Beryllium Solubility Hydrolysis and Sorption in Cementitious Systems, , 0, 0, - (2019)
  • 99Tc Sequestration Using NickelDoped Iron Spinel, , 0, 0, - (2019)
  • Immobilization of HighSulfate Radioactive Waste Solution by MetakaolinBased Geopolymer Wate Form, , 0, 0, - (2019)
  • 99Tc Immobilization by RedoxCoprecipitation with NickelDoped Iron Spinel from OffGas Waste Stream at Hanford Site, , 0, 0, - (2019)
  • Chemical Decontamination of Concrete Waste Generated from NPP Decommissioning, , 0, 0, - (2019)
  • Modification of GranularSized Natural Zeolite for Enhancing Practical Use, , 0, 0, - (2019)
  • Enhance Removal Efficiency of Cs Sr and Ni by Modifying Natural Zeolite to NaP Zeolite, , 0, 0, - (2019)
  • Decontamination of metal wastes using underwater microwave plasma, , 0, 0, - (2019)
  • Synthesis of bismuth functionalized graphene oxide and application for removal of radioactive iodine, , 0, 0, - (2019)
  • Uptake of BeII by ordinary Portland cement in the degradation phase I, , 0, 0, - (2019)
  • THERMAL TREATMENT OF RADIOACTIVE CONCRETE WASTES FROM NUCLEAR POWER PLANT DECOMMISSIONING, , 0, 0, - (2019)
  • SURFACE COMPLEXATION MODELING OF NICKEL SORPTION UNDER VARYING GEOCHEMICAL CONDITIONS, , 0, 0, - (2019)
  • Development of polymer waste form for spent ionexchange resins, , 0, 0, - (2019)
  • Solidification of HyBRID waste using metakaolin based geopolymer waste form, , 0, 0, - (2018)
  • Phase change of radioactive Co in radiologically contaminated concrete waste, , 0, 0, - (2018)
  • Leaching test for polymer waste form of spent ionexchange resins, , 0, 0, - (2018)
  • Surface Complexation Modeling of Nickel Sorption Under Varying Geochemical Conditions at the Wolsong Repository Site, 한국방사성폐기물학회 학술논문요약집, 0, 0, 247-248 (2018)
  • Overview of Radioactive Waste Acceptance Criteria for Treatment and Management of Radioactive Waste, 한국방사성폐기물학회 학술논문요약집, 0, 0, - (2018)
  • Radionuclides Removal Using Cancrinite and Chalcogel Sorbents, , 0, 0, - (2018)
  • Decontamination of Concrete Waste Gernerated from Nuclear Power Plant Decommissioning with Different Organic Solvents, , 0, 0, - (2018)
  • Resin Treatment Using Fenton Like Process With Cu Catalysis, , 0, 0, - (2018)
  • Treatment of Radionuclide from CRUD using Underwater Microwave Plasma, , 0, 0, - (2018)
  • Improving Radionuclide Retention in Cementitious Waste Forms through Controlled Mineral Growth, , 0, 0, - (2018)
  • Layered double hydroxides synthesis and application for radioactive iodine removal, , 0, 0, - (2018)
  • 99Tc Immobilization in Various Waste Forms, , 0, 0, - (2018)
  • Incorporation of Rhenium in Tin Dioxide for Technetium Immobilization, , 0, 0, - (2018)
  • NanoMinerals Plus Higher Temperatures Accelerate the Release and Transport of Carbon from Sediment, , 0, 0, - (2018)
  • Solidification of HyBRID Waste Using Geopolymer Waste Form, , 0, 0, - (2018)
  • Radiological Risk Assessment of 232Th and 238U in Water Leach Purification, , 0, 0, - (2018)
  • Solidification of spent resin for safe storage to repository, , 0, 0, - (2018)
  • Characterization and thermal treatment application for radioactive concrete wastes from nuclear power plant decommissioning, , 0, 0, - (2018)
  • Selective removal of radioactive iodine in waste water using bismuth functionalized graphene oxide, , 0, 0, - (2018)
  • Optimization of Heat Treatment Technique for Volume Reduction of Decommissioned Concrete Waste from Nuclear Power Plant, , 0, 0, - (2018)
  • Rheniumdoped tin dioxide study for technetium radioactive waste immobilization, 2018 춘계 지질과학기술 공동 국제학술대회 논문집, 0, 0, - (2018)
  • Iodine Analysis Optimization and Removal Study using Layered Double Hydroxides under Aqueous Condition, , 0, 0, - (2018)
  • Durable Tellurite Glasses for Vitrification of Technetium Wastes, WM 2018 SYMPOSIA, 0, 0, - (2018)
  • Cementitious Waste Form Development for Treatment of EMF Evaporator Bottoms, , 0, 0, - (2018)
  • Exploiting Knowledge of Technetium in the Subsurface to Develop Remediation Strategies, , 0, 0, - (2018)
  • Ni59 Sorption under Varying Geochemical Conditions at the Repository Site South Korea, , 0, 0, - (2018)
  • EDTA Effects on Reduction and Reoxidation of Rhenium Species For Possible Application to Technetium Radioactive Waste Management, , 0, 0, - (2018)
  • Memory Effect of Layered Double Hydroxides LDH to Remove Iodine Aqueous Species I and IO3, , 0, 0, - (2018)
  • Synthesis of geopolymer waste form to solidify radioactive wastes from decontamination of primary system in nuclear power plant, , 0, 0, - (2017)
  • Removal of Iodide and Iodate using Layered Double Hydroxides LDHs under Aqueous Condition , Removal of Iodide and Iodate using Layered Double Hydroxides LDHs under Aqueous Condition, 0, 0, - (2017)
  • Immobilization of radioactive waste generated from primary system decontamination using geopolymer waste form , Immobilization of radioactive waste generated from primary system decontamination using geopolymer waste form, 0, 0, - (2017)
  • Discovery of Stable Cyclic Rhenium Oxide Cluster An Analogues Studies for Technetium Removal , Discovery of Stable Cyclic Rhenium Oxide Cluster An Analogues Studies for Technetium Removal, 0, 0, - (2017)
  • Identifying Bacterial Communities and Their Correlations with Geochemical Parameters in Low and Intermediatelevel Radioactive Waste Disposal Facility in Republic of Korea , Identifying Bacterial Communities and Their Correlations with Geochemical Parameters in Low and Intermediatelevel Radioactive Waste Disposal Facility in Republic of Korea, 0, 0, - (2017)
  • Radionuclide transport in unsaturated fractured rock at LILW disposal facility , Radionuclide transport in unsaturated fractured rock at LILW disposal facility, 0, 0, - (2017)
  • Synthesis and Characterization of Rheniumethylenediaminetetraacetic Acid ReOEDTA Complexes to Understand the Technetiumorganic Aqueous Complexes Environmental Stability, Synthesis and Characterization of Rheniumethylenediaminetetraacetic Acid ReOEDTA Complexes to Understand the Technetiumorganic Aqueous Complexes Environmental Stability, 0, 0, - (2017)
  • Investigation of tributyl phosphatecoated hydroxyapatite for uranium removal, Investigation of tributyl phosphatecoated hydroxyapatite for uranium removal, 0, 0, - (2017)
  • Synthesis and Caracterization of Graphene oxide based material for Radioactive Iodine Removal, Synthesis and Caracterization of Graphene oxide based material for Radioactive Iodine Removal, 0, 0, - (2017)
  • Mechanisms for Simultaneous Tc and Cr Removal by FeOH2 in Hanford Waste Streams, ABSTRACTS OF PAPERS OF THE AMERICAN CHEMICAL SOCIETY, 0, 0, - (2017)
  • Effect of 99TcIV coprecipitation with respect to Fe minerals on 99Tc retention in glass, Effect of 99TcIV coprecipitation with respect to Fe minerals on 99Tc retention in glass, 0, 0, - (2017)
  • Investigation of 3H Tc99 and Sr90 transport in fractured rock and the effects of fractured fillingcoating material at LILW disposal facility, , 0, 0, - (2017)
  • Synthesis of graphene oxide based material for removing radioactive iodine , Synthesis of graphene oxide based material for removing radioactive iodine, 0, 0, - (2017)
  • Uranium removal by Tributyl PhosphateCoated Hydroxyapatite , Uranium removal by Tributyl PhosphateCoated Hydroxyapatite, 0, 0, - (2017)
  • The effect of fractured rock to radionuclides transport through unsaturated zone, , 0, 0, - (2017)
  • The effect of fractured rock to radionuclides transport through unsaturated zone, , 0, 0, - (2017)
  • The effect of fractured rock to radionuclides transport through unsaturated zone, , 0, 0, - (2017)
  • Sorption and transport behavior of radionuclide in unsaturated fractured rock at LILW disposal facility , Sorption and transport behavior of radionuclide in unsaturated fractured rock at LILW disposal facility, 0, 0, - (2017)
  • Competitive Binding Reaction and Sr Transport under Seawater Intrusion , Competitive Binding Reaction and Sr Transport under Seawater Intrusion, 0, 0, - (2017)
  • Removal Mechanism for Technetium 99Tc using FeOH2s at the Hanford Site WA USA, Removal Mechanism for Technetium 99Tc using FeOH2s at the Hanford Site WA USA, 0, 0, - (2017)
  • Use of Layered Double Hydroxide LDH Sorbents to Remove Radioactive Iodine Species, Waste management, 0, 0, - (2017)

Research Activities

  • , 경북도청 (2011-2019)
  • , (주)동아컨설턴트 (2012-2013)
  • , 주식회사미래와도전 (2012-2013)
  • , 한국원자력환경공단 (2012-2012)
  • , 한국과학기술연구원 (2013-2015)
  • , 주식회사 넥스지오 (2013-2014)
  • , (주)계림폴리콘 (2013-2013)
  • DEVELOPMENT OF PREDICTION MODEL FOR SR-90 TRANSPORT WITH SEAWATER INTRUSION, 재단법인한국연구재단 (2013-2014)
  • RADIONUCLIDES SORPTION AND COLUMN LABORATORY TESTS, (주)동아컨설턴트 (2013-2014)
  • , 포항공과대학교 (2014-2025)
  • , 포항공과대학교 (2014-2025)
  • , 한국원자력환경공단 (2014-2014)
  • DEVELOPMENT OF PREDICTION MODEL FOR SR-90 TRANSPORT WITH SEAWATER INTRUSION, 재단법인한국연구재단 (2014-2015)
  • , 포항공대산학협력단 (2014-2040)
  • DEVELOPMENT OF RADIONUCLIDE TRANSPORT MODEL THROUGH UNSATURATED ZONE IN COMPLEX LILW DISPOSAL FACILITY, 한국원자력환경공단 (2014-2015)
  • , 포항공과대학교 (2015-2025)
  • , 한국에너지기술평가원 (2015-2016)
  • DEVELOPMENT OF RADIONUCLIDE TRANSPORT MODEL THROUGH UNSATURATED ZONE IN COMPLEX LILW DISPOSAL FACILITY, 한국원자력환경공단 (2015-2016)
  • DEVELOPMENT OF PREDICTION MODEL FOR SR-90 TRANSPORT WITH SEAWATER INTRUSION, 재단법인한국연구재단 (2015-2016)
  • , 재단법인한국연구재단 (2015-2016)
  • , 한국원자력환경공단 (2015-2015)
  • , 한국원자력환경공단 (2016-2016)
  • , 재단법인한국연구재단 (2016-2017)
  • DEVELOPMENT OF RADIONUCLIDES TRANSPORT MODEL THROUGH UNSATURATED ZONE IN COMPLEX LILW DISPOSAL FACILITY, 한국원자력환경공단 (2016-2017)
  • , 포항공과대학교 (2017-2018)
  • , 포항공과대학교 (2017-2018)
  • , 포항공과대학교 (2017-2018)
  • SOLIDIFICATION OF RADIOACTIVE WASTE AFTER DECONTAMINATION OF PRIMARY SYSTEM, 한국원자력연구원 (2017-2017)
  • , 재단법인한국연구재단 (2017-2018)
  • TRITIUM SEPARATION USING QUANTUM SIEVE METHOD, 재단법인한국연구재단 (2017-2018)
  • , 한국원자력환경공단 (2017-2017)
  • , 포항공과대학교 (2017-2018)
  • , (주)산하이앤씨 (2017-2018)
  • DEVELOPMENT OF DECONTAMINATION METHOD TO REDUCE THE CONCRETE AND SOIL WASTES GENERATED FROM DECOMMISSIONING OF NPPS, 재단법인한국연구재단 (2017-2018)
  • , 주식회사 넥스지오 (2017-2018)
  • DEVELOPMENT OF CONTINUOUS TREATMENT SYSTEM FOR DECOMMISSIONING RADIOWASTE BASED ON MECHANOCHEMISTRY PROCESS, 한국에너지기술평가원 (2017-2018)
  • STUDY OF CONTAMINANT REMOVAL BY FE OXIDE TRANSFORMATION PROCESS, 재단법인한국연구재단 (2017-2018)
  • , 한국원자력연구원 (2018-2018)
  • R_간접비_첨단원자력공학부, 포항공과대학교 (2018-2025)
  • R_10137659_X-RAY DIFFRACTOMETER SYSTEM MINIFLEX 600, 포항공과대학교 (2018-2025)
  • , 포항공과대학교 (2018-2019)
  • , 재단법인한국연구재단 (2018-2019)
  • , 포항공과대학교 (2018-2019)
  • , (주)동아컨설턴트 (2018-2019)
  • DEVELOPMENT OF TREATMENT TECHNOLOGY FOR RADIOACTIVE WASTES GENERATED DURING NPP OPERATION, 한국수력원자력(주) (2018-2019)
  • DEVELOPMENT OF WASTE PACKAGE, TRANSPORTATION AND DISPOSAL CONTAINERS FOR DECOMMISSIONING WASTES OF NUCLEAR POWER PLANT, 한국에너지기술평가원 (2018-2018)
  • , 포항공과대학교 (2018-2032)
  • DEVELOPMENT OF DECONTAMINATION METHOD TO REDUCE THE CONCRETE AND SOIL WASTES GENERATED FROM DECOMMISSIONING OF NPPS, 재단법인한국연구재단 (2018-2019)
  • , 한국원자력환경공단 (2018-2018)
  • DEVELOPMENT OF CONTINUOUS TREATMENT SYSTEM FOR DECOMMISSIONING RADIOWASTE BASED ON MECHANOCHEMISTRY PROCESS, 한국에너지기술평가원 (2018-2019)
  • TREATMENT OF RADIONUCLIDE FROM CRUD USING UNDERWATER MICROWAVE PLASMA, 재단법인한국연구재단 (2018-2018)
  • , 경북도청 (2019-2019)
  • SOLIDIFICATION OF RADIOACTIVE WASTE AFTER DECONTAMINATION OF PRIMARY SYSTEM, 한국원자력연구원 (2019-2019)
  • , 경북도청 (2019-2019)
  • DEVELOPMENT OF WASTE PACKAGE, TRANSPORTATION AND DISPOSAL CONTAINERS FOR DECOMMISSIONING WASTES OF NUCLEAR POWER PLANT, 한국에너지기술평가원 (2019-2019)
  • , (주)산하이앤씨 (2019-2020)
  • , 포항공대산학협력단 (2019-2025)
  • , 재단법인한국연구재단 (2019-2020)
  • , 포항공과대학교 (2019-2020)
  • , 포항공과대학교 (2019-2019)
  • , 포항공과대학교 (2019-2020)
  • , 포항공과대학교 (2019-2020)
  • , 포항공과대학교 (2019-2020)
  • , (재)경북테크노파크 (2019-2020)
  • , (재)경북테크노파크 (2019-2020)
  • , 한국수력원자력(주) (2019-2020)
  • DEVELOPMENT OF DECONTAMINATION METHOD TO REDUCE THE CONCRETE AND SOIL WASTES GENERATED FROM DECOMMISSIONING OF NPPS, 재단법인한국연구재단 (2019-2020)
  • DEVELOPMENT OF TECHNOLOGY FOR 14C TREATMENT FROM SPENT RESIN AND THEIR STABILIZATION, 경상북도 (2019-2020)
  • DEVELOPMENT OF TECHNOLOGY FOR 14C TREATMENT FROM SPENT RESIN AND THEIR STABILIZATION, 재단법인한국연구재단 (2019-2020)
  • , 경상북도 (2019-2020)
  • DEVELOPMENT OF CONTINUOUS TREATMENT SYSTEM FOR DECOMMISSIONING RADIOWASTE BASED ON MECHANOCHEMISTRY PROCESS, 한국에너지기술평가원 (2019-2020)
  • , 한국원자력환경공단 (2019-2019)
  • , 현대엔지니어링(주) (2019-2021)
  • , 포항공대산학협력단 (2019-2040)
  • , 한국에너지기술평가원 (2020-2020)
  • , 경북도청 (2020-2020)
  • , 경북도청 (2020-2020)
  • , 포항공과대학교 (2020-2020)
  • DEVELOPMENT OF DECONTAMINATION METHOD TO REDUCE THE CONCRETE AND SOIL WASTES GENERATED FROM DECOMMISSIONING OF NPPS, 재단법인한국연구재단 (2020-2020)
  • , 재단법인한국연구재단 (2020-2021)
  • , 포항공과대학교 (2020-2025)
  • , 포항공과대학교 (2020-2025)
  • , 포항공과대학교 (2020-2025)
  • , 한국에너지기술평가원 (2020-2020)
  • , 경상북도 (2020-2021)
  • DEVELOPMENT OF TECHNOLOGY FOR 14C TREATMENT FROM SPENT RESIN, 재단법인한국연구재단 (2020-2021)
  • DEVELOPMENT OF TREATMENT TECHNOLOGY FOR RADIOACTIVE WASTES GENERATED DURING NPP OPERATION, 울산과학기술원 (2020-2021)
  • DEVELOPMENT OF OPTIMIZED SITE SELECTION STRATEGY BASED ON DRONE, 울산과학기술원 (2020-2021)
  • , 경상북도 (2020-2021)
  • DEVELOPMENT OF MULTI-PHASE THERMALHYDRAULIC NUMERICAL CODE BASED ON PARTICLE METHOD, 울산과학기술원 (2020-2021)
  • , (재)포항테크노파크 (2020-2021)
  • , 재단법인한국연구재단 (2021-2021)
  • , 한국에너지기술평가원 (2021-2021)
  • , 경북도청 (2021-2021)
  • , 포항공과대학교 (2021-2021)
  • , 재단법인한국연구재단 (2021-2022)
  • , 경상북도 (2021-2021)
  • , 재단법인한국연구재단 (2021-2022)
  • , 재단법인한국연구재단 (2021-2022)
  • , 경상북도 (2021-2022)
  • , 재단법인한국연구재단 (2021-2022)
  • , 경상북도 (2021-2022)
  • , 재단법인한국연구재단 (2021-2021)
  • , 재단법인한국연구재단 (2021-2021)
  • DEVELOPMENT OF BIOKINETIC AND RISK ASSESSMENT MODELS FOR HIGH-DISPERSIVE RADIOACTIVE CONTAMINANT INGESTION, 한국수력원자력(주) (2021-2022)
  • , 재단법인한국연구재단 (2022-2022)
  • , 재단법인한국연구재단 (2022-2022)
  • , 한국에너지기술평가원 (2022-2022)
  • , 재단법인한국연구재단 (2022-2022)
  • , 포항공과대학교 (2022-2022)
  • , 경상북도 (2022-2022)
  • , 경상북도 (2022-2022)
  • , 재단법인한국연구재단 (2022-2023)
  • , 재단법인한국연구재단 (2022-2023)
  • , 재단법인한국연구재단 (2022-2023)
  • , 재단법인한국연구재단 (2022-2023)
  • , 한국원자력환경공단 (2022-2022)
  • , 동국대학교경주산학협력단 (2022-2022)
  • DEVELOPMENT OF BIOKINETIC AND RISK ASSESSMENT MODELS FOR HIGH-DISPERSIVE RADIOACTIVE CONTAMINANT INGESTION, 한국수력원자력(주) (2022-2023)
  • , 포항공과대학교 (2022-2040)
  • , 현대엔지니어링(주) (2022-2024)
  • TESTING OF SOLUBILITY, SORPTION, AND DIFFUSION, OF NON-RADIOACTIVE ISOTOPES UNDER VARIOUS DISPOSAL ENVIRONMENTS, 재단법인한국연구재단 (2023-2023)
  • DEVELOPMENT OF HIGH PERFORMANCE BENTONITE USING SURFACE MODIFICATION AND LONG-TERM SAFETY ASSESSMENT, 재단법인한국연구재단 (2023-2023)
  • DEVELOPMENT OF WASTE PACKAGE, TRANSPORTATION AND DISPOSAL CONTAINERS FOR DECOMMISSIONING WASTES OF NUCLEAR POWER PLANT, 한국에너지기술평가원 (2023-2023)
  • , 포항공대산학협력단 (2023-2040)
  • , 재단법인한국연구재단 (2023-2024)
  • , 포항공과대학교 (2023-2024)
  • , 재단법인한국연구재단 (2023-2024)
  • , 재단법인한국연구재단 (2023-2024)
  • , 재단법인한국연구재단 (2023-2024)
  • , 재단법인한국연구재단 (2023-2024)
  • DEVELOPMENT OF BIOKINETIC AND RISK ASSESSMENT MODELS FOR HIGH-DISPERSIVE RADIOACTIVE CONTAMINANT INGESTION, 한국수력원자력(주) (2023-2024)
  • , (주)동아컨설턴트 (2023-2025)
  • , (주)어스이엔지 (2023-2025)
  • DEVELOPMENT OF HIGH PERFORMANCE BENTONITE USING SURFACE MODIFICATION AND LONG-TERM SAFETY ASSESSMENT, 한국원자력연구원 (2024-2024)
  • , 재단법인한국연구재단 (2024-2024)
  • , 한국원자력연구원 (2024-2024)
  • , 재단법인한국연구재단 (2024-2025)
  • , 재단법인한국연구재단 (2024-2025)
  • , 재단법인한국연구재단 (2024-2025)
  • , 재단법인한국연구재단 (2024-2025)
  • , 재단법인한국연구재단 (2024-2025)
  • , 한국원자력환경공단 (2024-2024)
  • , 한국원자력환경공단 (2024-2024)
  • TESTING OF SOLUBILITY, SORPTION, AND DIFFUSION, OF NON-RADIOACTIVE ISOTOPES UNDER VARIOUS DISPOSAL ENVIRONMENTS, 한국원자력연구원 (2025-2025)
  • DEVELOPMENT OF HIGH PERFORMANCE BENTONITE USING SURFACE MODIFICATION AND LONG-TERM SAFETY ASSESSMENT, 한국원자력연구원 (2025-2025)
  • , 한국원자력환경공단 (2025-2025)

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