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Kim, Hee Reyoung (김희령)

Department
Department of Nuclear Engineering(원자력공학과)
Website
http://kimhr.unist.ac.kr/
Lab
RAdiation and MagnetohydroDynamics Advanced Lab. (방사선안전 및 자기유체역학 연구실)
Research Keywords
원전해체, 방사선 안전, 초소형 원전 및 가속기 전자펌프, 플라즈마 신재생 발전, Nuclear, Nuclear D&D, MHD pump for micro reactor and accelerator, MHD plasma generation, Radiation monitoring
Research Interests
O Magnetohydrodynamics ApplicationThe research is focused on the magnetohydrodynamic (MHD)analysis and experimental characterization for the liquid metal transportation in fast reactor, accelerator, and MHD plasma electricity generation system for the future green energy. The MHD pump is also developed for circulation of lead and lithium target material on accelerated beam.O Environmental Radiation Safety and Nuclear DecommissioningThe research covers the establishment of the environmental radiation monitoring system around nuclear installations. The main interest is concerned with radiation monitoring and radioactivity analysis of the radioactive wastes from nuclear power plants. The D&D technology for the environmental restoration of the dismantled nuclear power plant (NPP) site is developed.
This table browses all dspace content
Issue DateTitleAuthor(s)TypeViewAltmetrics
2022-07Evaluation of radiological safety according to accident scenarios for commercialization of spent resin mixture treatment deviceChoi, Woo Nyun; Byun, Jaehoon; Kim, Hee ReyoungARTICLE306 Evaluation of radiological safety according to accident scenarios for commercialization of spent resin mixture treatment device
2022-05Applicability of a mobile in situ gamma detector with different scan speeds for evaluating hotspots in decommissioning sitesPark, Se-Won; Lee, Chanki; Kim, Hee ReyoungARTICLE237 Applicability of a mobile in situ gamma detector with different scan speeds for evaluating hotspots in decommissioning sites
2022-05Optimization of an Extra Vessel Electromagnetic Pump for Lead–Bismuth Eutectic Coolant Circulation in a Non-refueling Full-life Small ReactorKwak, Jaesik; Kang, Tae Uk; Kim, Hee ReyoungARTICLE188 Optimization of an Extra Vessel Electromagnetic Pump for Lead–Bismuth Eutectic Coolant Circulation in a Non-refueling Full-life Small Reactor
2022-03Feasibility study of synthesizing graphene quantum dots from the spent resin in a nuclear power plant to reduce disposal costYoon, Seungbin; Choi, Woo Nyun; Byun, Jaehoon, et alARTICLE194 Feasibility study of synthesizing graphene quantum dots from the spent resin in a nuclear power plant to reduce disposal cost
2022-03An Approach to the Localization of Technology for a Transport and Storage Container for Very Low-Level Radioactive Liquid WasteShin, Seung Hun; Choi, Woo Nyun; Yoon, Seungbin, et alARTICLE173 An Approach to the Localization of Technology for a Transport and Storage Container for Very Low-Level Radioactive Liquid Waste
2022-02Framework for the development of guidelines for nuclear power plant decommissioning workers based on risk informationHeo, Yunyeong; Lee, Choongwie; Kim, Hee Reyoung, et alARTICLE229 Framework for the development of guidelines for nuclear power plant decommissioning workers based on risk information
2022-02Tritium extraction in aluminum metal by heating method without meltingKang, Ki Joon; Byun, Jaehoon; Kim, Hee ReyoungARTICLE229 Tritium extraction in aluminum metal by heating method without melting
2022-02Evaluation of dose received by workers while repairing a failed spent resin mixture treatment deviceChoi, Woo Nyun; Byun, Jaehoon; Kim, Hee ReyoungARTICLE209 Evaluation of dose received by workers while repairing a failed spent resin mixture treatment device
2022-01Spatial Distribution Analysis and dose Assessment of the Radon Emitted from the Monazite-Containing Mattress in General Residential Space by CFD MethodsLee, Choong Wie; Kim, Hee ReyoungARTICLE161 Spatial Distribution Analysis and dose Assessment of the Radon Emitted from the Monazite-Containing Mattress in General Residential Space by CFD Methods
2021-12Radiological analysis of transport and storage container for very lowlevel liquid radioactive wasteShin, Seung Hun; Choi, Woo Nyun; Yoon, Seungbin, et alARTICLE188 Radiological analysis of transport and storage container for very lowlevel liquid radioactive waste
2021-12Preliminary Study on Rapid Measurement of Gross Alpha/Beta and 90Sr Activities in Surface Soil by Mobile ZnS(Ag)/PTV Array and Handheld PVT Rod with Gated Energy ChannelsLee Chanki; Kim, Hee ReyoungARTICLE175 Preliminary Study on Rapid Measurement of Gross Alpha/Beta and 90Sr Activities in Surface Soil by Mobile ZnS(Ag)/PTV Array and Handheld PVT Rod with Gated Energy Channels
2021-11Tritium radioactivity estimation in cement mortar by heat-extraction and liquid scintillation countingKang, Ki Joon; Bae, Jun Woo; Kim, Hee ReyoungARTICLE283 Tritium radioactivity estimation in cement mortar by heat-extraction and liquid scintillation counting
2021-11Dose evaluation of workers according to operating time and outflow rate in a spent resin treatment facilityByun, Jaehoon; Choi, Woo Nyun; Kim, Hee ReyoungARTICLE287 Dose evaluation of workers according to operating time and outflow rate in a spent resin treatment facility
2021-11Radioactivity analysis for EPS waste using organic solventsBae, Jun Woo; Kim, Hee ReyoungARTICLE189 Radioactivity analysis for EPS waste using organic solvents
2021-08Preliminary DCGLW for surface soil of Kori Unit-1 decommissioning site according to habit data and age of human receptorsPark, Se-Won; Kim, Hee ReyoungARTICLE235 Preliminary DCGLW for surface soil of Kori Unit-1 decommissioning site according to habit data and age of human receptors
2021-08Preliminary DCGL(W) for surface soil of Kori Unit-1 decommissioning site according to habit data and age of human receptorsPark, Se-Won; Kim, Hee ReyoungARTICLE188 Preliminary DCGL(W) for surface soil of Kori Unit-1 decommissioning site according to habit data and age of human receptors
2021-07Comparison of occupational exposure according to dismantling strategy of Kori nuclear power plant unit #1 bio-shieldLee, ChoongWie; Kim, Hee Reyoung; Lee, Seung JunARTICLE334 Comparison of occupational exposure according to dismantling strategy of Kori nuclear power plant unit #1 bio-shield
2021-06Radiological safety evaluation of dismantled radioactive concrete from Kori Unit 1 in the disposal and recycling processLee, ChoongWie; Kim, Hee Reyoung; Lee, Seung JunARTICLE382 Radiological safety evaluation of dismantled radioactive concrete from Kori Unit 1 in the disposal and recycling process
2021-06Accuracy comparison of fitting function applied to air-borne alpha detection spectrumSung, Si Hyeong; Kim, Min ji; Kim, Hee ReyoungARTICLE188 Accuracy comparison of fitting function applied to air-borne alpha detection spectrum
2021-05Numerical Analysis of the Temperature Distribution of the EM Pump for the Sodium Thermo-hydraulic Test Loop of the GenIV PGSFRKwak, Jaesik; Kim, Hee ReyoungARTICLE201 Numerical Analysis of the Temperature Distribution of the EM Pump for the Sodium Thermo-hydraulic Test Loop of the GenIV PGSFR

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