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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 6, Issue 4 - Dec 2008
Volume 6, Issue 3 - Sep 2008
Volume 6, Issue 2 - Jun 2008
Volume 6, Issue 1 - Mar 2008
Selecting the target year
Development of Electrokinetic-Flushing Equipment for a Remediation of Soil Contaminated with Radionuclides
Kim, Gye-Nam ; Jung, Yun-Ho ; Lee, Jung-Joon ; Moon, Jei-Kwon ; Jung, Chong-Hun ; Chung, Un-Soo ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 6, issue 1, 2008, Pages 1~9
This study examined the effect of an electrokinetic-flushing remediation for a soil of a high permeability. The soil was sampled from the site around a research atomic reactor which had high hydro-conductivities due to a high content of sand in the soil. The flow rate of the washing reagent was fast at the beginning but it was reduced as time lapsed. In the case of using citric acid as a washing reagent, the flow rate was fastest, 78.7 ml/day. The removal efficiencies of
from a soil cell with acetic acid were the highest, which were 95.2% and 84.2% respectively. The soil waste-solution volume generated from the electrokinetic remediation was reduced to about 1/20 of that from the soil washing remediation. Meanwhile, the electrokinetic-flushing method enhanced the removal efficiencies of
from the soil by about 6% and 2% respectively, compared to those by the electrokinetic method. Consequently, it was found that the electrokinetic-flushing method was more effective for the remediation of a soil with a high permeability.
Method for Determining Transportation Grade for HIC Containing Spent Resin Using Radioactivity Analysis
Kim, Tae-Wook ; Choi, Ki-Seop ; Kang, Ki-Doo ; Ha, Jong-Hyun ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 6, issue 1, 2008, Pages 11~15
In order to transport spent resin in a high integrated container made of high density polyethylene, a method for determining transportation grade by radioactivity analysis was developed. Ratios of radioisotopes in spent resin were derived from radioactivity analysis on spent resin. Associated curie-to-dose factors were determined to estimate radioisotope inventory from surface dose rates of spent resin. From the results, Activity limit of type A package was derived to be 1.19 TBq for HIC, and the corresponding surface dose rate was found to be 124.2 mSv/h.
A Study on Plasma Etching Reaction of Cobalt for Metallic Surface Decontamination
Jeon, Sang-Hwan ; Kim, Yong-Soo ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 6, issue 1, 2008, Pages 17~23
In this study, plasma processing of metal surface is experimentally investigated to enhance the surface decontamination efficiency and to find out the reaction mechanism. Cobalt, the major contaminant in the nuclear facilities, and three fluorine-containing gases,
are chosen for the investigation. Thin metallic disk specimens are prepared and their surface etching reactions with the three plasma gases are examined. Results show that the maximum etching rate of
is obtained with NF3 gas at
, while with
gas plasmas those of
are obtained, respectively. Along with etching experiments, constituent elements of the reaction products are identified to be cobalt, oxygen, and fluorine by AES (Auger Electron Spectroscopy) analysis. It turns out that the oxygen atoms are physically adsorbed ones to the surface from the ambient not participation ones during the analysis after reaction, which supports that the surface reaction of cobalt is mainly to be a fluorination reaction.
Selective Separation of Actinide(III) by a rPr-BTP/nitrobezene Extraction System
Lee, Eil-Hee ; Lim, Jae-Kwan ; Chung, Dong-Yong ; Yang, Han-Beom ; Kim, Kwang-Wook ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 6, issue 1, 2008, Pages 25~33
A selective separation of Actirlide(III) by a nPr-BTP/nitrobezene extraction system was studied. The nPr-BTP (2.6-Bis-(5.6-n-propyl-1.2.4-triazin-3-yl)-pyridine) of a environmentally -friendly CHN type was self-synthesized and its compatability with diluent and stability with nitric acid were investigated. At the 0.1M nPr-BTP/nitrobenzene-1M
and O/A=2, extraction yields of Am used as a representative of Actinide(III) and Eu were about 85% and 8%, respectively, and the other RE elements such as Nd, Ce and Y were extracted less than 3% (separation factor of Am and Eu was about 60). Thus, there was no problems in the selective extraction of Actinide(III) from RE. The stripping yield of Am with 0.05M
at O/A= 1, however, was about 43% and the maximum stripping yield was 65% at O/A=0.3. It is necessary to develop the stripping system including the stripping agent instead of nitric acid solution.
Conceptual Reactive Transport Modeling of Long-term Concrete Degradation and Uranium Solubility
Choi, Byoung-Young ; Koh, Yong-Kwon ; Kim, Geon-Young ; Yoo, Si-Won ; An, Sang-Won ; Bae, Dae-Seok ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 6, issue 1, 2008, Pages 35~44
Long-term degradation of coment barrier by diffusion was studied with reactive transport modeling. The result of modeling showed that cement barrier was altered about 30cm thickness after 50,000 years. The pH decreased from 13.0 to 11.9 because of depletion of alkali ions, and dissolution/precipitation of portlandite and CSH (Calcium Silicate Hydrate). In addition, porosity increased about 0.3 because of dissolution of portlandite and
. The solubility of uranium also increased with the increase of pe value The results of this study indicate that long-term degradation of comet can enhance the transport of nuclide by changing pH, pe, porosity in barrier.
A Study on Establishment of Buffer Zone of Radioactive Waste Repository
Yoon, Jeong-Hyoun ; Park, Joo-Wan ; Ju, Min-Su ; Kim, Chang-Lak ; Park, Jin-Baek ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 6, issue 1, 2008, Pages 45~54
A new proposed repository has a final capacity of 800,000 drums radioactive waste. Most of foreign repositories have a general practice of segregating control zones which mainly contributes to classification of degree of control, whether it is called buffer zone or not. Domestic regulatory requirements of establishment of buffer zone in a repository are not much different from those of nuclear power plants for operation period, in which satisfactory design objective or performance objective is the most important factor in determination of the buffer zone. The meaning of buffer zone after closure is a minimum requested area which can prevent inadvertant intruders from leading to non-allowable exposure during institutional control period. Safety assessment with drinking well scenario giving rise to the highest probability of exposure among the intruder's actions can verify fulfillment of the buffer zone which is determined by operational safety of the repository. At present. for the repository to be constructed in a few years, the same procedure and concept as described in this paper are applied that can satisfy regulatory requirements and radiological safety as well. However, the capacity of the repository will be stepwise extended upto 800,000 drums, consequently its layout will be varied too. Timely considerations will be necessary for current boundary of the buffer zone which has been established on the basis of 100,000 drums disposal.
Longevity Issues in Swelling Clay as a Buffer Material for a HLW Repository
Lee, Jae-Owan ; Cho, Won-Jin ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 6, issue 1, 2008, Pages 55~63
A swelling clay should remain physically and chemically stable for a long time to perform its functions as a buffer material of a high-level waste (HLW) repository. The longevity issues in the swelling clay were reviewed to evaluate their importance in the performance of a repository. The review results suggest that an elevated temperature due to decay heat, groundwater chemistry, high pH environment by concrete, organic matter and microbes, radiation, and mechanical disturbance might significantly affect the long-term performance of a swelling clay as a buffer material. This paper will be used as basic informations to design the swelling clay buffer for a HLW repository.
Analysis of the Spent Fuel Cooling Time for a Deep Geological Disposal
Lee, Jong-Youl ; Cho, Dong-Geun ; Choi, Heui-Joo ; Choi, Jong-Won ; Lee, Yang ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 6, issue 1, 2008, Pages 65~72
The purpose of the HLW deep geological disposal is to isolate and to delay the radioactive material release to human beings and the environment for a long time so that the toxicity does not affect to the environment. The main requirements for the HLW repository design is to keep the buffer temperature below
in order to maintain its integrity. So the cooling time of spent fuels discharged from the nuclear power plant is the key consideration factors for efficiency and economic feasibility of the repository. The disposal tunnel/disposal hole spacing, the disposal area and thermal capacity required for the deep geological repository layout which satisfies the temperature requirement of the disposal system is analyzed to set the optimized spent fuels cooling time. To do this, based on the reference disposal concept, thermal stability analyses of the disposal system have been performed and the derived results have been compared by setting the spent fuels cooling time and the disposal tunnel/disposal hole spacing in various ways. From these results, desirable spent fuels cooling time in view of disposal area is derived. The results shows that the time reaching the maximum temperature within the design limit of the temperature in the disposal site is likely shortened as the cooling time of spent fuels becomes short. Also it seems that the temperature-rising and-dropping patterns in the disposal site are of smoothly varying form as the cooling time of spent fuels becomes long. In addition, it is revealed that a desirable cooling time of spent fuels is approximately 40-50 years when spent fuels are supposedly disposed in the deep geological disposal site with its structural scale under consideration in this study.