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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 11, Issue 4 - Dec 2013
Volume 11, Issue 3 - Sep 2013
Volume 11, Issue 2 - Jun 2013
Volume 11, Issue 1 - Mar 2013
Selecting the target year
Improvement of Pilot-scale Electrokinetic Remediation Technology for Uranium Removal
Park, Hye-Min ; Kim, Gye-Nam ; Kim, Seung-Soo ; Kim, Wan-Suk ; Park, Uk-Ryang ; Moon, Jei-Kwon ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 11, issue 2, 2013, Pages 77~83
DOI : 10.7733/jkrws.2013.11.2.77
The original pilot-scale electrokinetic equipment suitable to soil contamination characteristics of Korean nuclear facility sites was manufactured for the remediation of soil contaminated with uranium. During the experiment with the original electrokinetic equipment, many metal oxides were generated and were stuck on the cathode plate. The uranium removal capability of the original electrokinrtic equipment was almost exhausted because the cathode plate covered with metal oxides did not conduct electricity in the original electrokinetic equipment. Therefore, the original electrokinetic equipment was improved. After the remediation experience for 25 days using the improved electrokinetic remediation equipment, the removal efficiency of uranium from the soil was 96.8% and its residual uranium concentration was 0.81 Bq/g. When the initial uranium concentration of soil was about 50 Bq/g, the electrokinetic remediation time required to remediate the uranium concentration below clearance concentration of 1.0 Bq/g was about 34 days. When the initial uranium concentration of soil was about 75 Bq/g, the electrokinetic remediation time required to remediate below 1.0 Bq/g was about 42 days. When the initial uranium concentration of soil was about 100 Bq/g, the electrokinetic remediation time required to remediate below 1.0 Bq/g was about 49 days.
Removal of Uranium by an Alkalization and an Acidification from the Thermal Decomposed Solid Waste of Uranium-bearing Sludge
Lee, Eil-Hee ; Yang, Han-Beom ; Lee, Keun-Young ; Kim, Kwang-Wook ; Chung, Dong-Yong ; Moon, Jei-Kwon ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 11, issue 2, 2013, Pages 85~93
DOI : 10.7733/jkrws.2013.11.2.85
This study has been carried out to elucidate the characteristics of the dissolution for Thermal Decomposed Solid Waste of uranium-bearing sludge (TDSW), the removal of impurities by an alkalization in a nitric acid dissolving solution of TDSW, and the selective removal (/recovery) of uranium by an acidification in an carbonate alkali solution, respectively. TDSW generated by thermal decomposition of U-bearing sludge which was produced in the uranium conversion plant operation, was stored in KAERI as a solid-powder type. It is found that the dissolution of TDSW is more effective in nitric acid dissolution than oxidative-dissolution with carbonate. At 1 M nitric acid solution, TDSW was undissolved about 30wt% as a solid residue, and uranium contained in TDSW was dissolved more than 99%. In order to the alkalization for the nitric acid dissolving solution of TDSW, carbonate alkalization is more effective with respect to remove the impurities. At the carbonate alkali solution controlled to about 9 of pH, Al, Ca, Fe and Zn co-dissolved with U in dissolution step was removed about
. On the other hand, U could be recovered more than 99% by an acidification at pH about 3 in a carbonate alkali solution, which was nearly removed the impurities, adding 0.5M
. It was found that uranium could be selectively recovered (/removed) from TDSW.
Existence and Characteristics of Microbial cells in the Bentonite to be used for a Buffer Material of High-Level Wastes
Lee, Ji Young ; Lee, Seung Yeop ; Baik, Min Hoon ; Jeong, Jong Tae ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 11, issue 2, 2013, Pages 95~102
DOI : 10.7733/jkrws.2013.11.2.95
There was a study for biological characteristics, except for physico-chemical and mineralogical properties, on the natural bentonite that is considered as a buffer material for the high-level radioactive waste disposal site. A bentonite slurry that was prepared from a local 'Gyeongju bentonite' in Korea was incubated in a serum bottle with nutrient media over 1 week and its stepwise change was observed with time. From the activated bentonite in the nutrient media, we can find a certain change of both solid and liquid phases. Some dark and fine sulfides began to be generated from dissolved sulfate solution, and 4 species of sulfate-reducing bacteria (SRB) were identified as living cells in samples that were periodically taken and incubated. These results show that sulfate-reducing (or metal-reducing) bacteria are adhering and existing in the powder of bentonite, suggesting that there may be a potential occurrence of longterm biogeochemical effects in and around the bentonite buffer in underground anoxic environmental conditions.
A-KRS GoldSim Model Verification: A Comparison Study of Performance Assessment Model
Lee, Youn-Myoung ; Jeong, Jongtae ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 11, issue 2, 2013, Pages 103~114
DOI : 10.7733/jkrws.2013.11.2.103
The Korea Atomic Energy Research Institute has developed a performance assessment model implementing the A-KRS concept, which was constructed with the GoldSim. In the A-KRS concept, spent nuclear fuel produced from pressurized-water-reactor operations would be pyroprocessed to reduce waste volume and radioactivity. The wastes to be disposed of in a geologic repository are comprised of metal and ceramic waste forms. In this study, results of simulations conducted to establish credibility and build confidence for the A-KRS model are presented. Specifically, release rates and breakthrough times simulated using the A-KRS model were compared to corresponding results from the U.S. NRC SOAR model. In addition, the A-KRS model results were compared to published release rates from the SKB repository performance assessment. This comparison of the A-KRS model results to other independent performance assessments is expected to form part of a suite of model verification and validation activities to provide confidence that the A-KRS model has been implemented appropriately.
Development of Site Characterization Technologies for Crystalline Rocks at Mizunami Underground Research Laboratory (MIU) - Surface-based Investigation Phase -
Hama, Katsuhiro ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 11, issue 2, 2013, Pages 115~131
DOI : 10.7733/jkrws.2013.11.2.115
The Mizunami Underground Laboratory (MIU) Project is a comprehensive research project investigating the deep underground environment within crystalline rock being conducted by Japan Atomic Energy Agency. The MIU Project has three overlapping phases: Surface-based Investigation phase (Phase I), Construction phase (Phase II), and Operation phase (Phase III), with a total duration of 20 years. The overall project goals of the MIU Project from Phase I through to Phase III are: 1) to establish techniques for investigation, analysis and assessment of the deep geological environment, and 2) to develop a range of engineering for deep underground application. For the overall project goals 1), the Phase I goals were set to construct models of the geological environment from all surface-based investigation results that describe the geological environment prior to excavation and predict excavation response. For the overall project goals 2), the Phase I goals were set to formulate detailed design concepts and a construction plan for the underground facilities. This paper introduces geosynthesis procedures for the investigation and assessment of the hydrochemistry of groundwater in crystalline rock.
Research Status and Roles of Natural Analogue Studies in the Radioactive Waste Disposal
Baik, Min-Hoon ; Park, Tae-Jin ; Kim, In-Young ; Choi, Kyung-Woo ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 11, issue 2, 2013, Pages 133~156
DOI : 10.7733/jkrws.2013.11.2.133
Natural analogue studies play an important role in the safety case which requires multiple lines of evidence including the safety assessment for the geological disposal of radioactive wastes. In this study, foreign status of natural analogue studies was investigated by summarizing natural analogue results according to the research topics related with repository materials and radionuclide migration and retardation. Main results, issues, and applicability of the foreign natural analogue studies were also analyzed. The results of domestic natural analogue studies were classified into studies using uranium ore bodies, rocks, groundwaters, and archeological artifacts, respectively, and their main results were summarized. There are massive materials for natural analogue studies which have been carried out during last several decades but they have not been actively applied to the safety assessment and safety case development for the radioactive waster disposal. Thus, in this study, applicable methods of natural analogues were summarized and a methodology for improving their applicability was examined. Natural analogue study is apparently necessary to improve and illustrate the reliability of safety assessment for a radioactive waste repository. Therefore, it is necessary to develop a methodology and construct a natural analogue information database for the application of the results from natural analogue studies to safety case development.
Preliminary Review on Function, Needs and Approach of Underground Research Laboratory for Deep Geological Disposal of Spent Nuclear Fuel in Korea
Bae, Dae-Seok ; Koh, Yong-Kwon ; Lee, Sang-Jin ; Kim, Hyunjoo ; Choi, Byong-Il ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 11, issue 2, 2013, Pages 157~178
DOI : 10.7733/jkrws.2013.11.2.157
This study gives a conceptual and basic direction to develop a URL (underground research laboratory) program for establishing the performance and safety of a deep geological disposal system in Korea. The concept of deep geological disposal is one of the preferred methodologies for the final disposal of spent nuclear fuel (SNF). Advanced countries with radioactive waste disposal have developed their own disposal concepts reasonable to their social and environmental conditions and applied to their commercial projects. Deep geological disposal system is a multi-barrier system generally consisting of an engineered barrier and natural barrier. A disposal facility and its host environment can be relied on a necessary containment and isolation over timescales envisaged as several to tens of thousands of years. A disposal system is not allowed in the commercial stage of the disposal program without a validation and demonstration of the performance and safety of the system. All issues confirming performance and safety of a disposal system include investigation, analysis, assessment, design, construction, operation and closure from planning to closure of the deep geological repository. Advanced countries perform RD&D (research, development & demonstration) programs to validate the performance and safety of a disposal system using a URL facility located at the preferred rock area within their own territories. The results and processes from the URL program contribute to construct technical criteria and guidelines for site selection as well as suitability and safety assessment of the final disposal site. Furthermore, the URL program also plays a decisive role in promoting scientific understanding of the deep geological disposal system for stakeholders, such as the public, regulator, and experts.