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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
The Study for Reducing the Borrowing Cost for LILW Disposal
Kim, Beomin ; Kim, Chang-Lak ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 12, issue 2, 2014, Pages 89~96
DOI : 10.7733/jnfcwt.2014.12.2.89
The repository for the disposal of LILW which is generated from nuclear power plants and industries is expected to be completed in 2014. For the disposal of LILW, it is important to secure a disposal facility itself, but it is also very important to establish a reasonable charging system which all shareholders are satisfied with. Korea`s disposal fee for LILW is higher than other countries` fee, which is a burden to waste generators as well as the waste management organization. The partial reason for the high disposal fee is put on the high social and construction cost when compared with other countries. However the major reason is put on the excessive borrowing cost that is used for the construction of the LILW disposal facility. In this study, we proposed the way to reduce the excessive borrowing cost for sustainable project managements of LILW disposal by analyzing a cost structure.
Feasibility about the Direct Measurement of
Ra Using the Gamma-Ray Spectrometry
Ji, Young-Yong ; Chung, Kun Ho ; Lim, Jong-Myoung ; Kim, Change-Jong ; Jang, Mee ; Kang, Mun Ja ; Park, Sang Tae ; Woo, Zuhee ; Koo, Boncheol ; Seo, Bokyun ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 12, issue 2, 2014, Pages 97~105
DOI : 10.7733/jnfcwt.2014.12.2.97
In the case of the direct measurement of
using a HPGe gamma-ray spectrometer, the interference between gammarays with 186.21 keV of
and 185.7 keV of
should be corrected to calculate the net peak area in the energy spectrum. In general, it is very difficult to conduct peaks stripping with difference of about 0.5 keV, although a HPGe with the superior resolution is applied and the maximum channels is applied to the spectrometer. In this study, several interference correction techniques in the direct measurement were surveyed to evaluate the feasibility for the measurement of
using the gamma-ray spectrometery. Applying the interference corrections to the analysis of raw materials and by-products, the method validation for the direct measurement of
was conducted by evaluating the measurement uncertainty, linearity, and range. As a result, the optimum method of the interference correction was selected by comparing with the indirect measurement of which progenies of
, such as
, were analyzed in the secular equilibrium state.
Overseas Review on the In-situ Demonstration of EBS for IN-DEBS Development
Lee, Minsoo ; Choi, Heui-Joo ; Lee, Jong-Youl ; Lee, Changsoo ; Lee, Jae-Owan ; Kim, Inyoung ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 12, issue 2, 2014, Pages 107~119
DOI : 10.7733/jnfcwt.2014.12.2.107
The worldwide Status-of-Art survey for the in-situ experiments of the engineered barrier system for HLW underground disposal was performed as a preliminary action for the design of the in-situ demonstration at KURT. Some nations, which have executed or is ongoing the in-situ experiments at their underground research facilities, were summarized in this review. The demonstration projects reviewed were TBT/Sweden-France, LOT/Sweden, HE-E/Switzerland, PRACLAY/Belgium, FEBEX/Spain, HORONOBE/Japan, and BCE/Canada. The investigated items for the projects were mainly their purposes, constitutional structures, test conditions, monitoring parameters and the measuring tools, and test results. In this review, the hardware design and the assembling of the test system were more concentrated rather than their experimental results, because the purpose of this review is to achieve the necessary information for the practical design of the in-situ experiment to be installed at KURT. A mid scale in-situ demonstration of EBS at KURT, that is called IN-DBES, will be launched right after the completion the expanding project of KURT in 2015. It is hoped that the structural design, installing methods, hardware equipments required in the establishment of IN-DEBS will be referred on this review.
A Foreign Cases Study of the Deep Borehole Disposal System for High-Level Radioactive Waste
Lee, Jongyoul ; Kim, Geonyoung ; Bae, Daeseok ; Kim, Kyeongsoo ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 12, issue 2, 2014, Pages 121~133
DOI : 10.7733/jnfcwt.2014.12.2.121
If the spent fuels or the high-level radioactive wastes can be disposed of in the depth of 3~5 km and more stable rock formation, it has several advantages. For example, (1)significant fluid flow through basement rock is prevented, in part, by low permeability, poorly connected transport pathways, and (2)overburden self-sealing. (3)Deep fluids also resist vertical movement because they are density stratified and reducing conditions will sharply limit solubility of most dose-critical radionuclides at the depth. Finally, (4) high ionic strengths of deep fluids will prevent colloidal transport. Therefore, as an alternative disposal concept to the deep geological disposal concept(DGD), very deep borehole disposal(DBD) technology is under consideration in number of countries in terms of its outstanding safety and cost effectiveness. In this paper, for the preliminary applicability analyses of the DBD system for the spent fuels or high level wastes, the DBD concepts which have been developed by some countries according to the rapid advance in the development of drilling technology were reviewed. To do this, the general concept of DBD system was checked and the study cases of foreign countries were described and analyzed. These results will be used as an input for the analyses of applicability for DBD in Korea.
Understanding and Their Application of GoldSim Transport Pathways to Mass Trasport Simulation
Lee, Youn-Myoung ; Jeong, Jongtae ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 12, issue 2, 2014, Pages 135~151
DOI : 10.7733/jnfcwt.2014.12.2.135
It is very important to properly understand such "Transport Pathways" elements as "Pipe" and "Cell" pathways in commercial GoldSim Transport Module (GTM) for developing higer quality models and programs for performance assessment of complex radioactive waste repositories. With an illustrative case under an earthquake scenario, by which an increasement in the groundwater flow rate occurs though the geological medium, ways of avoiding possible modeling errors in the nuclide transport modeling in the radioactive waste repository system for its safety assessment by utilizing such pathways are discussed and a proper usage of the pathways is proposed.
A Study on Radioactive Source-term Assessment Method for Decommissioning PWR Primary System
Song, Jong Soon ; Kim, Hyun-Min ; Lee, Sang-Heon ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 12, issue 2, 2014, Pages 153~164
DOI : 10.7733/jnfcwt.2014.12.2.153
Currently, there are many programs which are now being developed or already developed to predict radionuclide and corrosion product at the stage of designing NPP. However, since there are not many developments in evaluating quantity of activation corrosion products occurring when disassembling a nuclear power plant there exist some difficulties in calculating accurately. In order to evaluate activation products inventory for the research of effect of neutron activation in the reactor vessel, component of nuclear reactor and adjacent structures, it should be evaluated by using operation history of nuclear reactor, material composition of structure and average neutron flux in every field representing fixed structure of nuclear reactor. In this study, CORA, PACTOLE, CRUDSIM, CREAT and ACE codes are analyzed to predict the quantity of radionuclide and corrosion product of primary reactor which is used at the stage of designing. As a future study, the accuracy in calculating the quantity of product corrosion can be increase by finding out the possibility of use and improvement for evaluation of the decontamination.
Review of the Acceptance Criteria of Very Low Level Radioactive Waste for the Disposal of Decommissioning Waste
Kim, Beomin ; Kim, Chang-Lak ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 12, issue 2, 2014, Pages 165~169
DOI : 10.7733/jnfcwt.2014.12.2.165
In order to use the nuclear energy as the sustainable energy source, the safe and efficient management of radioactive wastes generated from the nuclear fuel cycle including NPP decommissioning is one of the most important factors. The establishment of acceptance criteria for very low level radioactive wastes generated from decommissioning of nuclear power plant in a large quantity is seemed to play a key role for developing a radioactive wastes disposal strategy as well as NPP decommissioning strategy. In this thesis, we want to review the acceptance criteria of low-and-intermediate-level radioactive wastes in this country through the analysis of other country`s acceptance criteria.
Assessment of the Radiological Inventory for the Reactor at Kori NPP Using In-Situ Measurement Technology
Jeong, Hyun Chul ; Jeong, Sung Yeop ;
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT), volume 12, issue 2, 2014, Pages 171~178
DOI : 10.7733/jnfcwt.2014.12.2.171
After the expiration of operating license of a plant, all infrastructures within the plant must be safely dismantled to the point that it no longer requires measures for radiation protection. Despite the fact that Kori 1 and Wolsong 1 are close to the expiration of their operating license, sufficient technologies for radiological characterization, decontamination and dismantling is still under development. The purpose of this study is to develop one of methods for radiological inventory assessment on measuring object by using direct measure of large component with In-Situ measurement technique. Radiological inventory was assessed by analyzing nuclide using portable gamma spectroscopy without dismantling reactor head, and the result of direct measurement was supplemented by performing indirect measurement. Radiochemical analysis were performed on surface contamination samples as well. During the study, radiological inventory of reactor vessel calculated expanding the result. Based on the result and the radioactivity variation of each radionuclides time frame for decommissioning can be decided. Thus, it is expected that during the decommissioning of plants, the result of this study will contribute to the reduction of radiation exposure to workers.