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REFERENCE LINKING PLATFORM OF KOREA S&T JOURNALS
> Journal Vol & Issue
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
Journal Basic Information
Journal DOI :
The Korean Radioactive Waste Society
Editor in Chief :
Volume & Issues
Volume 12, Issue 4 - Dec 2014
Volume 12, Issue 3 - Sep 2014
Volume 12, Issue 2 - Jun 2014
Volume 12, Issue 1 - Mar 2014
Selecting the target year
Improved Treatment Technique for the Reuse of Waste Solution Generated from a Electrokinetic Decontamination System
Kim, Wan-Suk ; Kim, Seung-Soo ; Kim, Gye-Nam ; Park, Uk-Ryang ; Moon, Jei-Kwon ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 12, issue 1, 2014, Pages 1~6
DOI : 10.7733/jnfcwt.2014.12.1.1
A large amount of acidic waste solution is generated from the practical electrokinetic decontamination equipments for the remediation of soil contaminated with uranium. After filtration of uranium hydroxides formed by adding CaO into the waste solution, the filtrate was recycled in order to reduce the volume of waste solution. However, when the filtrate was used in an electrokinetic equipment, the low permeability of the filtrate from anode cell to cathode cell due to a high concentration of calcium made several problems such as the weakening of a fabric tamis, the corrosion of electric wire and the adhension of metallic oxides to the surface of cathode electrode. To solve these problems, sulfuric acid was added into the filtrate and calcium in the solution was removed as
precipitate. A decontamination test using a small electrokinetic equipment for 20 days indicated that Ca-removed waste solution decreased uranium concentration of the waste soil to 0.35 Bq/g, which is a similar to a decontamination result obtained by distilled water.
Performance Evaluation to Develop an Engineering Scale Cathode Processor by Multiphase Numerical Analysis
Yoo, Bung Uk ; Park, Sung Bin ; Kwon, Sang Woon ; Kim, Jeong Guck ; Lee, Han Soo ; Kim, In Tae ; Lee, Jong Hyeon ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 12, issue 1, 2014, Pages 7~17
DOI : 10.7733/jnfcwt.2014.12.1.7
Molten salt electrorefining process achieves uranium deposits at cathode using an electrochemical processing of spent nuclear fuel. In order to recover pure uranium from cathode deposit containing about 30wt% salt, the adhered salt should be removed by cathode process (CP). The CP has been regarded as one of the bottle-neck of the pyroprocess as the large amount of uranium is treated in this step and the operation parameters are crucial to determine the final purity of the product. Currently, related research activities are mainly based on experiments consequently it is hard to observe processing variables such as temperature, pressure and salt gas behavior during the operation of the cathode process. Hence, in this study operation procedure of cathode process is numerically described by using appropriate mathematical model. The key parameters of this research are the amount of evaporation at the distillation part, diffusion coefficient of gas phase salt in cathode processor and phase change rate at condensation part. Each of these conditions were composed by Hertz-Langmuir equation, Chapman-Enskog theory, and interphase mass flow application in ANSYS-CFX. And physical properties of salt were taken from the data base in HSC Chemistry. In this study, calculation results on the salt gas behavior and optimal operating condition are discussed. The numerical analysis results could be used to closely understand the physical phenomenon during CP and for further scale up to commercial level.
A Sensitivity Study on Nuclide Release from the Near-field of the Pyroprocessed Waste Repository System: Part 1. A Probabilistic Approach
Lee, Youn-Myoung ; Jeong, Jongtae ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 12, issue 1, 2014, Pages 19~35
DOI : 10.7733/jnfcwt.2014.12.1.19
A parametric sensitivity to the annual exposure dose rate to the farming exposure group has been probabilistically carried out for three principal elements associated with the nuclide transport behavior in the near-field of the pyroprocessed waste repository system. Credit time for both metal and ceramic containers, annual nuclide release rete, and the degree of loss of bentonite buffer around the container are selected as the elements and investigated for important nuclides. All the elements are shown to be sensitive to the results. Methodology studied through this study and the results are expected to make a good feedback to the repository design. As a follow-up study, separated in Part 2, the A-KRS will be deterministically assessed and then compared among each other with the normal, the worst, and the best case scenarios associated with their extreme values these elements could have.
A Sensitivity Study on Nuclide Release from the Near-field of a Pyroprocessed Waste Repository System: Part 2. A Deterministic Approach
Lee, Youn-Myoung ; Jeong, Jongtae ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 12, issue 1, 2014, Pages 37~43
DOI : 10.7733/jnfcwt.2014.12.1.37
A parametric sensitivity to the annual exposure dose rate to the farming exposure group has been deterministically carried out for three principal elements identified in the near-field of the pyroprocessed waste repository system as a series study of Part 1 of the coupled paper with the same title. Credit time for both metal and ceramic containers, annual nuclide release rete and the degree of loss of bentonite buffer around the container are selected and investigated deterministically for important nuclides. To this end the A-KRS has been assessed and then compared among each other with the normal, the worst, and the best case scenarios associated with their extreme values these elements could have. All the elements are shown to be sensitive to the results as was in Part 1. Methodology studied through this study and the results are expected to make a good feedback to the repository design.
A Review on the Application of Ionic Liquids for the Radioactive Waste Processing
Park, Byung Heung ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 12, issue 1, 2014, Pages 45~57
DOI : 10.7733/jnfcwt.2014.12.1.45
Academic interests in ionic liquid (IL) technologies have been extended to the nuclear industry and the applicability of ionic liquids for processing radioactive materials have been investigated by many researchers. A number of studies have reported interesting results with respect to the spectroscopic and electrochemical behaviors of metal elements included in spent nuclear fuels. The measured and observed properties of metal ions in TBP(tri-butyl phosphate) dissolved ILs have led the development of alternative technologies to traditional aqueous processes. On the other hand, the electrochemical deposition of metal ions in ILs have been investigated for the application of the solvents to aqueous as well as to non-aqueous processes. In this work, a review on the application of ILs in nuclear fuel cycle is presented for the purpose of categorizing and summarizing the notable researches on ILs.
Study on the Institutional Control Period Through the Post-drilling Scenario Of Near Surface Disposal Facility for Low and Intermediate-Level Radioactive Waste
Hong, Sung-Wook ; Park, Jin-Baek ; Yoon, Jung-Hyun ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 12, issue 1, 2014, Pages 59~68
DOI : 10.7733/jnfcwt.2014.12.1.59
The public's access to the disposal facilities should be restricted during the institutional control period. Even after the institutional control period, disposal facilities should be designed to protect radiologically against inadvertent human intruders. This study is to assess the effective dose equivalent to the inadvertent intruder after the institutional control period thorough the GENII. The disposal unit was allocated with different kind of radioactive waste and the effects of the radiation dose to inadvertent intruder were evaluated in accordance with the institutional control period. As a result, even though there is no institutional control period, all were satisfied with the regulatory guide, except for the disposal unit with only spent filter. However, the disposal unit with only spent filter was satisfied with the regulatory guide after the institutional control period of 300 years. But the disposal unit with spent filter mixed with dry active waste could shorten the institutional control period. So the institutional control period can be reduced through the mixing the other waste with spent filter in disposal unit. Therefore, establishing an appropriate plan for the disposal unit with spent filter and other radioactive waste will be effective for radiological safety and reduction of the institutional control period, rather than increasing the institutional control period and spending costs for the maintenance and conservation for the disposal unit with only spent filter.
The Method for Evaluating Unsaturated Hydraulic Conductivity of the Bentonite-buffer Using Relative Humidity
Lee, Hang-Bok ; Kim, Jin-Seop ; Choi, Young-Chul ; Choi, Heui-Joo ; Kim, Kyungsu ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 12, issue 1, 2014, Pages 69~77
DOI : 10.7733/jnfcwt.2014.12.1.69
Unsaturated hydraulic conductivity of the bentonite-buffer was evaluated using the relative humidity data. The method for calculating unsaturated hydraulic conductivity was deduced from the general analytical equation representing the movement of water in unsaturated media, which was applied to the experimental results of water infiltration tests for identifying the behavior of unsaturated hydraulic conductivity according to the water saturation. Unlike the saturated condition, the hydraulic gradient and water flux were irregularly changed, and the unsaturated hydraulic conductivity was increased with increasing the experimental time. Swelling of bentonite grains due to the water absorption increased the volume and size of pore within bentonite, resulting in the increase of water velocity and unsaturated hydraulic conductivity. This result suggested the necessity of further investigation on the correlation between the swelling degree of bentonite-buffer and unsaturated hydraulic conductivity. The method used in this study can be useful technique for evaluating long-term hydraulic performance of bentonite-buffer in the radioactive waste disposal system.
Smart Decontamination Device for Small-size Radioactive Scrap Metal Waste : Using Abrasion pin in Rotating Magnetic Field and Ultrasonic Wave Cleaner
Hong, Yong-Ho ; Park, Su-Ri ; Han, Sang-Wook ; Kim, Byung-Jick ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 12, issue 1, 2014, Pages 79~88
DOI : 10.7733/jnfcwt.2014.12.1.79
We have developed a smart decontamination device for small-size radioactive scrap metal (SSRSM) necessarily generated from nuclear facilities. This is a multi-modal device such as rotation of magnetic field focusing on the region containing the abrasion pins placed around target and ultrasonic cleaner. Additionally, in order to increase the decontamination efficiency we have modified some configuration of the device so that it could work on them evenly and totally. With the Optimal operating for operation of the new device, we tried to decontaminate some various metal selected as a sample during 15 minutes sequentially using each method, magnetic and ultrasonic device. As a result, the range of decontamination factor has been highly increased to 18~56. After decontamination, all samples were found its activity less than background level.