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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
Estimation of Groundwater Level Fluctuation of the Crystalline site Using Time Series Analyses in South Korea
Lee, Jeong-Hwan ; Jung, Haeryong ; Lee, Eunyong ; Kim, Sujeong ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 11, issue 3, 2013, Pages 179~192
DOI : 10.7733/jnfcwt-k.2013.11.3.179
This study is characterized the groundwater flow pattern near crystalline site of Yangbook-Myeon, Gyeong-ju City, South Korea. From the time series analyses, groundwater level could be classified into 4 types reflecting the hydrogeological characteristics and rainfall pattern. The type I (DB1-1, DB1-2) may be directly influenced by rainfall pattern. The type II (DB1-3, DB1-7, KB-1, KB-2, KB-3, KB-7, KB-14, KB-15) may be influenced by rainfall event as well as groundwater flow through water-conducting features. The type III (DB-5, DB1-6, DB2-2, KB-10, KB-11, KB-13) may be predominantly happens in the crystaline rock mass, groundwater in this type flows through the minor fracture networks rather than direct effect of rainfall event. The type IV (DB1-8, KB-9) may be influenced by irregular variation of the groundwater level due to anisotropy and heterogeneity of crystalline rock.
Influence of pH and Ionic Strength on Treatment of Radioactive Boric Acid Wastes by Forward Osmosis Membrane
Choi, Hye-Min ; Hwang, Doo-Seong ; Lee, Kune-Woo ; Moon, Jei-Kwon ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 11, issue 3, 2013, Pages 193~198
DOI : 10.7733/jnfcwt-k.2013.11.3.193
In general, boron recovery of 40-90% could be achieved by Reverse Osmosis (RO) membranes in neutral pH condition. As an emerging technology, Forward Osmosis (FO) membrane has attracted growing interest in wastewater treatment and desalination. The objective of this study is to evaluate the possibility of the boron removal in radioactive liquid waste by FO. In this study, the performance of FO was investigated to remove boron in the simulated liquid waste as the factors such as pH, osmotic pressure, ionic strength of solution, etc. The pH of feed solution is a major operating parameter which strongly influences to the permeation of boron and more than 80% of boron content can be separated when conducted at pH values less than 7. The water flux is not influenced but the boron flux and permeation rate tends to decrease in the low salt concentration of 1,000 mg/L. The boron flux increases linearly, but the permeation ratio of reducing boron is nearly constant even with changes in the draw solution concentration.
A study on the electrodeposition of uranium using a liquid cadmium cathode at 440℃ and 500℃
Yoon, Jong-Ho ; Kim, Si-Hyung ; Kim, Gha-Young ; Kim, Tack-Jin ; Ahn, Do-Hee ; Paek, Seungwoo ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 11, issue 3, 2013, Pages 199~206
DOI : 10.7733/jnfcwt-k.2013.11.3.199
Electrowinning process in pyroprocessing recovers U (uranium) and TRU (Trans Uranium) elements simultaneously from spent fuels using a liquid cadmium cathode (LCC). When the solubility limit of U deposits over 2.35wt% in Cd, U dendrites were formed on the LCC surface during the electrodeposition at
. Due to the high surface area of dendritic U, the deposits were not submerged into the liquid cadmium pool but grow out of the LCC crucible. Since the U dendrites act as a solid cathode, it prevents the co-deposition of U and TRUs. In this study, the electrodeposition of U onto a LCC was carried out at 440 and
to compare the morphology and component of U deposits. The U deposits at
have a specific shape and were stacked regularly at the center of the LCC pool, while the U dendrites (i.e.,
were grow out of the LCC crucible. Through the microscopic observation and XRD analysis, the electrodeposits at
, which have a round shape, were identified as an intermetallic compound such as
. It can be concluded that the LCC electrowinning operation at
achieves the co-recovery of U and TRU without the formation of U dendrites.
A Research on the Economic Feasibility of Korean Nuclear Power under the Condition of Social Acceptance after Fukushima Accident
Kim, Dong-Won ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 11, issue 3, 2013, Pages 207~212
DOI : 10.7733/jnfcwt-k.2013.11.3.207
Since the Fukushima nuclear power plant accident in March 2011, critical views on the increase in operation of nuclear power plants including the safety and the economic feasibility thereof have been expanding across the world. In these circumstances, we are to find out solutions to the controversial questions on whether nuclear power plants are economically more feasible than other energy sources, while the safety thereof is fully maintained. Thereby, nuclear power plants will play a key role as a sustainable energy source in the future as well as at present. To measure the social safety level that Korean people are actually feeling after the Fukushima accident, a method of cost-benefit analysis called the Contingent Valuation Method(CVM) was used, whereby we wanted to estimate the amount of expenses the general public would be willing to pay for the safety based on their acceptance rather than the social safety. As a result of calculating the trade-off value of the economic feasibility versus the safety in nuclear power plants through the survey thereon, it caused the nuclear power generation cost to be increased by 4.75 won/kWh. Reflecting this on the current power generation cost of 39.11 won/kWh would increase the cost to 43.86 won/kWh. It is thought that this potential cost is still more competitive than the coal-fired power generation cost of 67 won/kWh. This result will be available as a basic data for the 2nd Energy Basic Plan to be drawn up this year, presenting policy implications at the same time.
Development of the draft guidelines of the decommissioning plan for a nuclear power plant in Korea
Lee, Jungmin ; Moon, Joohyun ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 11, issue 3, 2013, Pages 213~227
DOI : 10.7733/jnfcwt-k.2013.11.3.213
It is essential to prepare the decommissioning plan for a nuclear power plant (NPP) for the safe decommissioning of the NPP, minimization of the generation of decommissioning wastes, and protection of human beings and environment. Although Kori unit 1 and Wolsong unit 1 will be destined to their decommissioning in Korea in the near future. there is no provisons about preparing the decommissioning plan. In this paper, therefore, the draft guidelines of the decommissioning plan for a NPP were developed by considering the domestic situation, based on the comparative analyses of the regulatory guidelines of the decommissioning plan in U.S., U.K. and France. The draft guidelines are expected to play an important role to modify the domestic laws and regulations on the decommissioning of the NPP, and to give a license holder in charge of decommissioning the detailed instructions for preparing it in advance.
In Situ Solute Migration Experiments in Fractured Rock at KURT: Installation of Experimental System and In Situ Solute Migration Experiments
Lee, Jae-Kwang ; Baik, Min-Hoon ; Lee, Tae-Yeop ; Park, Kyung-Woo ; Jeong, Jongtae ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 11, issue 3, 2013, Pages 229~243
DOI : 10.7733/jnfcwt-k.2013.11.3.229
An in situ solute migration system was designed and installed in KAERI Underground Research Tunnel (KURT) constructed in the site of Korea Atomic Energy Research Institute (KAERI) in order to investigate the migration and retardation of non-sorbing and sorbing tracers through a rock fracture. The system is composed of three main parts including injection, extraction, and data treatment. For the selection of a water-conducting fracture, boreholes were drilled. The fractures in the drilled boreholes were investigated using borehole image analysis using borehole image processing system (BIPS). The results of BIPS analysis showed that borehole YH 3-1 and YH 3-2 were connected each other. Moreover, hydraulic tests were carried out to determine the test section with connectivity for the in situ experiments. The in situ solute migration experiments were accomplished to understand the migration of solutes through fractures in KURT using non-sorbing tracers which were fluorescein sodium, eosin-B, bromide and sorbing tracers which were rubidium, nickel, zirconium, and samarium.
Determinations of the Exposure Rate Using a NaI(Tl) Detector of the Environmental Radiation Monitor
Ji, Young-Yong ; Lee, Wanno ; Choi, Sang-Do ; Chung, Kun Ho ; Kang, Mun Ja ; Choi, Geun-Sik ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 11, issue 3, 2013, Pages 245~251
DOI : 10.7733/jnfcwt-k.2013.11.3.245
The energy band and the G-factor method were compared to determine the exposure rate from the measured spectrum using a NaI(Tl) scintillation detector. First, G-factors of a 3"
" NaI(Tl) detector mounted to a EFRD 3300, which means the environmental radiation monitor, in Korea Atomic Energy Research Institute (KAERI) were calculated for several directions of incident photons through the MCNP modeling, and the optimum G-factor applicable to that monitor was then determined by comparing the results both the energy band method and the G-factor method. The results for these spectrometric determinations were also compared with the dose rate from a HPIC radiation monitor around a EFRD 3300. The measured value at the EFRD 3300 based on a 3"
" NaI(Tl) detector was
and its difference was shown about
, when compared with the results from a HPIC radiation moditor. Since a HPIC is known to be able to measure cosmic rays with the relatively high energy, the difference between them was caused by cosmic rays which were not detected in a 3"
" NaI(Tl) detector.
Analysis of Siting Criteria of Overseas Geological Repository (II): Hydrogeology
Jung, Haeryong ; Kim, Hyun-Joo ; Cheong, Jae-Yeol ; Lee, Eun Yong ; Yoon, Jeong Hyoun ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 11, issue 3, 2013, Pages 253~257
DOI : 10.7733/jnfcwt-k.2013.11.3.253
Geology, hydrogeology, and geochemistry are the main technical siting factors of a geological repository for spent nuclear fuels. This paper evaluated the siting criteria of overseas geological repository with related to hydrogeologic properties, such as hydraulic conductivity, partitioning coefficient, dispersion coefficient, boundary condition, and water age. Each country establishes the siting criteria based on its important geological backgrounds and information, and social environment. For example, Sweden and Finland that have decided a crystalline rock as a host rock of a geological repository show different siting criteria for hydraulic conductivity. In Sweden, it is preferable to avoid area where the hydraulic conductivity on a deposition hole scale (~30m) exceeds
, whereas Finland does not decide any criterion for the hydraulic conductivity because of limited data for it. In addition, partitioning coefficients should be less than 10-1 of average value in Swedish crystalline bedrock. However, the area where shows 100 times less than average partitioning coefficients of radionuclides in crystalline rock should be avoided in Sweden. In German, the partitioning coefficients for the majority of the long-term-relevant radionuclides should be greater than or equal to
. Therefore, it is strongly required to collect much and exact information for the hydrogeologic properties in order to set up the siting criteria.