Hee‐Chul Eun
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View article: Decontamination of a Contaminated RCP Shaft Using the SP-HyBRID Process
Decontamination of a Contaminated RCP Shaft Using the SP-HyBRID Process Open
It is very important to minimize the waste generation for decontamination of the reactor coolant system in a nuclear facility. As an alternative to commercial decontamination technologies, an inorganic acid chemical decontamination (SP-HyB…
View article: Decontamination of corrosion oxides in the heat transport system of a pressurized heavy water reactor using chelate-free inorganic acid
Decontamination of corrosion oxides in the heat transport system of a pressurized heavy water reactor using chelate-free inorganic acid Open
Thick corrosion oxide (Fe3O4) layers containing radioactive metals are generated in a carbon steel heat transport system (HTS) of pressurized heavy water reactors during operation. It is necessary to decontaminate the oxide layers to reduc…
View article: Hydrazine Radiolysis by Gamma-Ray in the N2H4–Cu+–HNO3 System
Hydrazine Radiolysis by Gamma-Ray in the N2H4–Cu+–HNO3 System Open
Radiolysis of chemical agents occurs during the decontamination of nuclear power plants. The γ-ray irradiation tests of the N2H4–Cu+–HNO3 solution, a decontamination agent, were performed to investigate the effect of Cu+ ion and HNO3 on N2…
View article: Behaviors of Perfluorocarbon Emulsion during Dissolution of Oxide Layers
Behaviors of Perfluorocarbon Emulsion during Dissolution of Oxide Layers Open
This study investigates the dissolution behavior of oxide layers containing radionuclides using perfluorocarbon (PFC) emulsion as a reusable medium. Chemicals such as PFC, anionic surfactant, and H2SO4 are used for preparing the PFC emulsi…
View article: Development of Carbonization and a Relatively High-Temperature Halogenation Process for the Removal of Radionuclides from Spent Ion Exchange Resins
Development of Carbonization and a Relatively High-Temperature Halogenation Process for the Removal of Radionuclides from Spent Ion Exchange Resins Open
This study investigated a two-step thermochemical treatment process consisting of carbonization and halogenation for the removal of radionuclides from spent cation-exchange resin (CER). Based on a thermal analysis of cation-exchange resins…
View article: Thermal Decontamination of Spent Activated Carbon Contaminated with Radiocarbon and Tritium
Thermal Decontamination of Spent Activated Carbon Contaminated with Radiocarbon and Tritium Open
The thermal desorption of tritium (3H, T) and radiocarbon (14C) from spent activated carbon was investigated and three thermal desorption steps were established: the vaporization of homogeneously condensed molecules, the desorption of mole…
View article: Removal and Decomposition of Impurities in Wastewater From the HyBRID Decontamination Process of the Primary System in a Nuclear Power Plant
Removal and Decomposition of Impurities in Wastewater From the HyBRID Decontamination Process of the Primary System in a Nuclear Power Plant Open
Decontamination wastewater generated from the HyBRID decontamination process of the primary system in a nuclear power plant contains impurities such as sulfate ions, metal ions containing radioactive nuclides, and hydrazine (carcinogenic a…
View article: Colorimetric Method for Detection of Hydrazine Decomposition in Chemical Decontamination Process
Colorimetric Method for Detection of Hydrazine Decomposition in Chemical Decontamination Process Open
The aim of nuclear facility decommissioning is to make local settlements safe, sustainable and professedly acceptable. The challenges are the clean-up of the nuclear site and waste management. This means a definite promise in terms of safe…
View article: Capture and Solidification of Rare Earth Nuclide (Nd) in LiCl-KCl Eutectic Salt Using a Synthetic Inorganic Composite
Capture and Solidification of Rare Earth Nuclide (Nd) in LiCl-KCl Eutectic Salt Using a Synthetic Inorganic Composite Open
In this study, neodymium (Nd) nuclides in LiCl-KCl eutectic salts were captured and solidified using a synthetic inorganic composite (Li2O-SiO2-Al2O3-B2O3), a process that allows the selective capture of Nd and fabrication of a composite w…
View article: A Basic Study on Capture and Solidification of Rare Earth Nuclide (Nd) in LiCl-KCl Eutectic Salt Using an Inorganic Composite With Li2O-Al2O3-SiO2-B2O3 System
A Basic Study on Capture and Solidification of Rare Earth Nuclide (Nd) in LiCl-KCl Eutectic Salt Using an Inorganic Composite With Li2O-Al2O3-SiO2-B2O3 System Open
사용후핵연료 파이로프로세싱에서는 방사성 희토류 염화물(RECl3)을 함유한 LiCl-KCl 공융염폐기물이 발생되며, 핫셀시설 에서 운영을 목적으로 단순한 형태의 공융염폐기물 처리공정을 개발하는 것이 필요하다. 본 연구에서는, LiCl-KCl 공융염폐 기물 내 희토류 핵종 분리/고화공정의 단순화를 목적으로 Li2O-Al2O3-SiO2-B2O3계의 무기합성매질을 이용하여 LiCl-KCl 공융 염 내 희토류 핵종(Nd)을 분리한 …
View article: A Study on the Trapping Characteristics of Rhenium Oxide Using Ca(OH)2
A Study on the Trapping Characteristics of Rhenium Oxide Using Ca(OH)2 Open
The objective of this study was to obtain basic data for trapping gaseous technetium (Tc) oxide generated from the voloxidation process in spent nuclear fuel pyroprocessing.Rhenium (Re) and Ca(OH)2 were used as surrogates for the technetiu…
View article: A Study on the Separation and Solidification of Group II Nuclides from LiCl Waste Salt Generated from a Pyrochemical Process
A Study on the Separation and Solidification of Group II Nuclides from LiCl Waste Salt Generated from a Pyrochemical Process Open
Waste treatment technology for the separation and solidification of radioactive nuclides generated from the pyrochemical process has been intensively studied to achieve the reduction of radioactive waste volume. The present study reports t…
View article: Separation Characteristics of NdCl3 from LiCl-KCl Eutectic Salt in a Reactive Distillation Process using Li2CO3 or K2CO3
Separation Characteristics of NdCl3 from LiCl-KCl Eutectic Salt in a Reactive Distillation Process using Li2CO3 or K2CO3 Open
It is necessary to develop an effective waste salt treatment technology for the minimization of radioactive waste generation from the pyroprocessing of spent nuclear fuel. For this reason, the separation characteristics of NdCl3 from LiCl-…
View article: A Preliminary Study on the Feasibility of Copper Mesh as an Off-Gas Iodine Capturing Medium for Pyroprocessing
A Preliminary Study on the Feasibility of Copper Mesh as an Off-Gas Iodine Capturing Medium for Pyroprocessing Open
A commercially available copper mesh was investigated as an iodine off-gas capturing medium for pyroprocessing, with an aim to replace costly silver based adsorbents. Theoretical calculation results suggested that the reaction between meta…