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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 10, Issue 4 - Dec 2012
Volume 10, Issue 3 - Sep 2012
Volume 10, Issue 2 - Jun 2012
Volume 10, Issue 1 - Mar 2012
Selecting the target year
A Study on the Development of the FEP and Scenario for the HLW Disposal in Korea
Kang, Chul-Hyung ; Jeong, Jong-Tae ; Choi, Jong-Won ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 10, issue 3, 2012, Pages 133~141
DOI : 10.7733/jkrws.2012.10.3.133
The impacts influenced on the performance and safety of a repository are classified as units of Features, Events, and Processes (FEP), for the total system performance assessment (TSPA) related to the permanent disposal of HLW. The importance is evaluated in consideration of the frequency, consequence, regulation, suitability of a specific site, etc. and then these are grouped as a similar FEP. A scenario describing the migration of radionuclide from the repository to the biosphere is derived from understanding the interaction among these groups. KAERI has developed the KAERI FEP lists by review and collation of the foreign studies. The KAERI FEP list has been reviewed by several Korean experts. The five major scenarios describing possible future evolutions of the geological disposal system have been developed by RES and PID methods. Also the CYPRUS which is a KAERI integrated database management system for the total system performance assessment (TSPA) related to the permanent disposal of HLW has been developed and the results of the FEP and scenario development have been uploaded in this system.
Groundwater Flow Modeling in the KURT site for a Case Study about a Hypothetical Geological Disposal Facility of Radioactive Wastes
Ko, Nak-Youl ; Park, Kyung Woo ; Kim, Kyung Su ; Choi, Jong Won ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 10, issue 3, 2012, Pages 143~149
DOI : 10.7733/jkrws.2012.10.3.143
Groundwater flow simulations were performed to obtain data of groundwater flow used in a safety assessment for a hypothetical geological disposal facility assumed to be located in the KURT (KAERI Underground Research Tunnel) site. A regional scale modeling of the groundwater flow system was carried out to make boundary conditions for a local scale modeling. And, fracture zones identified at the study site were involved in the local scale groundwater flow model. From the results of the local scale modeling, a hydraulic head distribution was indicated and it was used in a particle tracking simulation for searching pathway of groundwater from the location of the hypothetical disposal facility to the surface where the groundwater reached. The flow distance and discharge rate of the groundwater in the KURT site were calculated. It was thought that the modeling methods used in this study was available to prepare the data of groundwater flow in a safety assessment for a geological disposal facility of radioactive wastes.
Potential repository domain for A-KRS at KURT facility site
Kim, Kyung-Su ; Park, Kyung-Woo ; Kim, Geon-Young ; Choi, Heui-Joo ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 10, issue 3, 2012, Pages 151~159
DOI : 10.7733/jkrws.2012.10.3.151
The potential repository domains for A-KRS (Advanced Korean Reference Disposal System for High Level Wastes) in geological characteristics of KURT (KAERI Underground Research Tunnel) facility site were proposed to develop a repository system design and to perform the safety assessment. The host rock of KURT facility site is one of major Mesozoic plutonic rocks in Korean peninsula, two-mica granite, which was influenced by hydrothermal alteration. The topographical features control the flow lines of surface and groundwater toward south-easterly and all waters discharge to Geum River. Fracture zones distributed in study site are classified into order 2 magnitude and their dominant orientations are N-S and E-W strike. From the geological features and fracture zones, the potential repository domains for A-KRS were determined spatially based on the following conditions: (1) fracture zone must not cross the repository; and (2) the repository must stay away from the fracture zones greater than 50 m. The western region of the fracture zones in the N-S direction with a depth below 200 m from the surface was sufficient for A-KRS repository. Because most of the fracture zones in N-S direction were inclined toward the east, we expected to find a homogeneous rock mass in the western region rather than in the eastern region. The lower left domain of potential domains has more suitable geological and hydrogeological conditions for A-KRS repository.
Production and Application of Domestic Input Data for Safety Assessment of Disposal
Park, Chung-Kyun ; Lee, Jae-Kwang ; Baik, Min-Hoon ; Lee, Youn-Myoung ; Ko, Nak-Youl ; Jeong, Jong-Tae ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 10, issue 3, 2012, Pages 161~170
DOI : 10.7733/jkrws.2012.10.3.161
To provide domestic values of input parameters in a safety assessment of radioactive waste disposal under domestic deep underground environments, various kinds of experiments have been carried out under KURT (KAERI Underground Research Tunnel) conditions. The input parameters were classified, and some of them were selected for this study by the criteria of importance. The domestic experimental data under KURT environments were given top priority in the data review process. Foreign data under similar conditions to KURT were also gathered. The collected data were arranged and the statistical calculations were processed. The properties and distribution of the data were explained and compared to foreign values in view of their validity. The following parameters were analysed: failure time and early time failure rate of a container, solubility of nuclides, porosity and density of the buffer, and distribution coefficients of nuclides in the geomedia, hydraulic conductivity, diffusion depth of nuclides, groundwater flow rate, fracture aperture, length of internal fracture, and width of faulted rock mass in the host rock.
A Deterministic Safety Assessment of a Pyro-processed Waste Repository
Lee, Youn-Myoung ; Jeong, Jongtae ; Choi, Jongwon ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 10, issue 3, 2012, Pages 171~188
DOI : 10.7733/jkrws.2012.10.3.171
A GoldSim template program for a safety assessment of a hybrid-typed repository system, called "A-KRS," in which two kinds of pyro-processed radioactive wastes, low-level metal wastes and ceramic high-level wastes that arise from the pyro-processing of PWR nuclear spent fuels are disposed of, has been developed. This program is ready both for a deterministic and probabilistic total system performance assessment which is able to evaluate nuclide release from the repository and farther transport into the geosphere and biosphere under various normal, disruptive natural and manmade events, and scenarios. The A-KRS has been deterministically assessed with 5 various normal and abnormal scenarios associated with nuclide release and transport in and around the repository. Dose exposure rates to the farming exposure group have been evaluated in accordance with all the scenarios and then compared among other.
Geochemical Characterization of Rock-Water Interaction in Groundwater at the KURT Site
Ryu, Ji-Hun ; Kwon, Jang-Soon ; Kim, Geon-Young ; Koh, Yong-Kwon ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 10, issue 3, 2012, Pages 189~197
DOI : 10.7733/jkrws.2012.10.3.189
Geochemical composition of fracture filling minerals and groundwater was investigated to characterize geochemical characteristics of groundwater system at the KURT site. Minerals such as calcite, illite, laumontite, chlorite, epidote, montmorillonite, and kaolinite, as well as I/S mixed layer minerals were detected in the minerals extracted from the fracture surfaces of the core samples. The groundwater from the DB-1, YS-1 and YS-4 boreholes showed alkaline conditions with pH of higher than 8. The electrical conductivity (EC) values of the groundwater samples were around
, except for the YS-1 borehole. Dissolved oxygen was almost zero in the DB-1 borehole indicating highly reduced conditions. The Cl- concentration was estimated around 5 mg/L and showed homogeneous distribution along depths at the KURT site. It might indicate the mixing between shallow groundwater and deep groundwater. The shallow groundwater from boreholes showed
type, whereas deep groundwater below 300 m from the surface indicated
type. The isotopic values observed in the groundwater ranged from -10.4 to -8.2‰ for
and from -71.3 to -55.0‰for
. In addition, the isotope-depleted water contained higher fluoride concentration. The oxygen and hydrogen isotopic values of deep groundwater were more depleted compared to the shallow groundwater. The results from age dating analysis using
indicated relatively younger (2000~6000yr old) groundwater compared to other european granitic groundwaters such as Stripa (Sweden).
Hydrogeological Properties of Geological Elements in Geological Model around KURT
Park, Kyung Woo ; Kim, Kyung Su ; Koh, Yong Kwon ; Choi, Jong Won ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 10, issue 3, 2012, Pages 199~208
DOI : 10.7733/jkrws.2012.10.3.199
To develop site characterization technologies for a radioactive waste disposal research in KAERI, the geological and hydrogeological investigations have been carried out since 1997. In 2006, the KURT (KAERI Underground Research Tunnel) was constructed to study a solute migration, a microbiology and an engineered barrier system as well as deeply to understand geological environments in in-situ condition. This study is performed as one of the site characterization works around KURT. Several investigations such as a lineament analysis, a borehole/tunnel survey, a geophyscial survey and logging in borehole, were used to construct the geological model. As a result, the geological model is constructed, which includes the lithological model and geo-structural model in this study. Moreover, from the results of the in-situ hydraulic tests, the hydrogeological properties of elements in geological model were evaluated.
Design, Manufacturing, and Performance estimation of a Disposal Canister for the Ceramic Waste from Pyroprocessing
Lee, Minsoo ; Choi, Heui-Joo ; Lee, Jong-Youl ; Choi, Jong-Won ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 10, issue 3, 2012, Pages 209~218
DOI : 10.7733/jkrws.2012.10.3.209
A pyroprocess is currently being developed by KAERI to cope with a highly accumulated spent nuclear fuel in Korea. The pyroprocess produces a certain amount of high-level radioactive waste (HLW), which is solidified by a ceramic binder. The produced ceramic waste will be confined in a secure disposal canister and then placed in a deep geologic formation so as not to contaminate human environment. In this paper, the development of a disposal canister was overviewed by discussing mainly its design premises, constitution, manufacturing methods, corrosion resistance in a deep geologic environment, radiation shielding, and structural stability. The disposal canister should be safe from thermal, chemical, mechanical, and biological invasions for a very long time so as not to release any kind of radionuclides.
A Study on the Conceptual Development for a Deep Geological Disposal of the Radioactive Waste from Pyro-processing
Lee, Jong-Youl ; Lee, Min-Soo ; Choi, Heui-Joo ; Bae, Dae-Seok ; Kim, Kyeong-Soo ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 10, issue 3, 2012, Pages 219~228
DOI : 10.7733/jkrws.2012.10.3.219
A long-term R&D program for HLW disposal technology development was launched in 1997 in Korea and Korea Reference disposal System(KRS) for spent fuels had been developed. After then, a recycling process for PWR spent fuels to get the reusable material such as uranium or TRU and to reduce the volume of radioactive waste, called Pyro-process, is being developed. This Pyro-process produces several kinds of wastes including metal waste and ceramic waste. In this study, the characteristics of the waste from Pyro-process and the concepts of a disposal container for the wastes were described. Based on these concepts, thermal analyses were carried out to determine a layout of the disposal area of the ceramic wastes which was classified as a high level waste and to develop the disposal system called A-KRS. The location of the final repository for A-KRS is not determined yet, thus to review the potential repository domains, the possible layout in the geological characteristics of KURT facility site was proposed. These results will be used in developing a repository system design and in performing the safety assessment.