• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.12 no.4
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• pp.267-274
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• 2014

The first Low- and Intermediate-Level Waste (LILW) disposal facility with 6 silos has been constructed in granite host rock saturated with groundwater in Korea. A two-dimensional numerical modeling on gas migration was carried out using TOUGH2 with EOS5 module in the disposal facility. Laboratory-scale experiments were also performed to measure the important properties of silo concrete related with gas migration. The gas entry pressure and relative gas permeability of the concrete was determined to be $0.97{\pm}0.15bar$ and $2.44{\times}10^{-17}m^2$, respectively. The results of the numerical modeling showed that hydrogen gas generated from radioactive wastes was dissolved in groundwater and migrated to biosphere as an aqueous phase. Only a small portion of hydrogen appeared as a gas phase after 1,000 years of gas generation. The results strongly suggested that hydrogen gas does not accumulate inside the disposal facility as a gas phase. Therefore, it is expected that there would be no harmful effects on the integrity of the silo concrete due to gas generation.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.15 no.4
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• pp.369-380
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• 2017

In order to manage the uncertainty about the evaluation and analysis of the human intrusion scenario of the Gyeongju Low and Intermediate Level Radioactive Waste(LILW) disposal facility, the calculation result by the GENII code was assessed using the RESRAD code, which was developed to evaluate the radiation effects of contaminated soil. The post-drilling scenario was selected as a human intrusion scenario into the near-surface disposal facility to analyze the uncertainty of the modeling by identifying any limitations in the simulation of each code and comparing the evaluation results under the same input data conditions. The results revealed a difference in the migration of some nuclides between the codes, but confirmed that the dose trends at the end of the post-closure control period were similar for all exposure pathways. Based on the results of the dose evaluation predicted by RESRAD, sensitivity analysis on the input factors was performed and major input factors were derived. The uncertainty of the modeling results and the input factors were analyzed and the reliability of the safety evaluation results was confirmed. The results of this study can be applied to the implementation 'Safety Case Program' for the Gyeongju LILW disposal facility.

• KSCE Journal of Civil and Environmental Engineering Research
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• v.26 no.3D
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• pp.491-497
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• 2006

The goal of this research is to explore the opinions of the resident's neighboring within sewage disposal plants, to investigate the differences in accordance with each location of sewage disposal plants, and to examine the determinants to impact on the sewage disposal plants. The multivariate analysis of variance model and regression model are employed as the empirical analysis for this research. The major findings are as follows; as a rule, most of residents represented the sewage disposal plants are essential public facilities. The sewage disposal plants could be positively considered under proper compensation and negotiation, It is found that the satisfaction level against accomplishing process of the sewage disposal plants facilities are very low. In addition, it was revealed that the determinants to impact on the sewage disposal plants showed differently according to each current location of sewage disposal plants. It means that there are no absolutely concrete reasons to oppose the sewage disposal plants and they can be somewhat different by the each local characteristics. Therefore, these findings provide for the policy makers related with the NIMBY facilities including the sewage disposal plants with valuable information.

• Journal of Radiation Protection and Research
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• v.27 no.2
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• pp.111-120
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• 2002

A reference scenario of vault safety case prepared by the IAEA for the near-surface disposal facility of low-and informed]ate-level radioactive wastes is assessed with the MASCOT program. The appropriate conceptual models for the MASCOT implementation is developed. An assessment of groundwater pathway through a drinking well as a geosphere-biosphere interface is performed first. then biosphere pathway is analysed to estimate the radiological consequences of the disposed radionuclides based on compartment modeling approach. The validity of conceptual modeling for the reference scenario is investigated where possible comparing to the results generated by the other assessment. The result of this study shows that the typical conceptual model for groundwater pathway represented by the compartment model ran be satisfactorily used for safety assessment of the entire disposal system in a cons]stent way. It is also shown that safety assessment of a disposal facility considering complex and various pathways would be possible by the MASCOT program.

• Journal of the Korean Home Economics Association
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• v.38 no.9
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• pp.107-118
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• 2000

This study was carried out to obtain the information concerning the behavior and underlying consciousness of housewives about the disposal of foods waste and to find out relationships among environmental variables. Data were obtained through questionnaires and interviews from 350 housewives in Ulsan area. Foods waste can be produced at every stage of cooking. It was found that the most amount of foods waste was produced at the preparation stage of cooking. The type of dishes which produces the most waste was chigas. About 49.4% of foods waste consisted of vegetables and fruits and 18.5% of that was fishes. The environmental concern related to foods waste disposal was relatively high among subjects and they were willing to accept foods waste reducing system if it is not too complicated to use and not too expensive. These results have demonstrated that menu planning before food preparation and buying cleaned and trimmed materials in the market should be highly recommended to reduce the foods waste. To improve the disposal behavior of foods waste, it is required that well programmed education for environmental conservation and the public facility for foods waste disposal.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05b
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• pp.441-446
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• 1998

As for safety assessment of a radioactive waste disposal facility, radiation dose to inadvertent intruders is evaluated according to scenarios related to intruder's postulated activities at the disposal site after the end of Institutional Control Period(ICP). Simple trench and Below Ground Vault(BGV) are considered for this study as alternative disposal systems, and different scenarios are applied to each disposal type. The results show that 300 years of ICP is needed for simple trench and 100 years for BGV. Even for BGV, concentration of long-lived radioactive nuclides should be limited considering degradation of BGV after 300 years.

• Journal of Environmental Impact Assessment
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• v.28 no.3
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• pp.312-331
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• 2019

An offshore waste disposal facility refers to a landfill site for final landfilling of stabilized inorganic solid waste such as land and marine waste incineration materials, and the aim of such a facility is to solve the problem of insufficient waste disposal space on land and create and develop environmentally friendly marine spaces. The purpose of this study is to prepare guidelines for the construction of offshore waste disposal facilities, which reflect the need and importance of paying sufficient heed to environmental considerations from the initial stage of the project, in order to investigate, predict, and assess how such guidelines will affect the marine environment in relation to the construction of offshore waste disposal facilities, with the goal of minimizing the impact on and damage to the environment. For the purpose of this research, guidelines focusing on the construction of offshore waste disposal facilities were derived through an analysis of domestic cases and similar foreign cases and an assessment of their level of compliance with existing EIA guidelines through the operation of a discussion forum. In order to review the EIA report on similar cases in Korea, 17 EIA documents (2005~2016) for dredged soil dumping areas and ash ponds of thermal power plants were analyzed to investigate the status of marine organisms, marine physics, marine water quality, and marine sediment and to understand what types of problems can occur and what improvement measures can be taken. The purpose of these guidelines were to minimize damage to the marine environment by promoting EIA protocols in accordance with scientific and systematic procedures, to reduce the consultation period related to projects, to resolve social conflicts, and to reduce economic costs.

• Tunnel and Underground Space
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• v.32 no.2
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• pp.107-119
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• 2022

Excavation-Disturbed Zone (EDZ) is an important design factor in constructing final disposal facilities for spent nuclear fuel, since EDZ affects mechanical stability including a spacing between disposal holes, and the hydraulic properties within EDZ plays a significant role in estimating in-flow rate of groundwater as well as a subsequent corrosion rate of a canister. Thus, it is highly required to characterize in-situ EDZ with precision and control the EDZ occurrence while excavating disposal facilities and constructing relevant underground research facilities. In this report, we not only reviewed EDZ-related researches carried out in the ONKALO facility of Finland but also examined appropriate methods for field inspection and quality control of EDZ occurrence. From the review, GPR can be the most efficient method for in-situ characterization of EDZ since it does not demand drilling a borehole that may disturb a surrounding environment of caverns. And the EDZ occurrence was dominant at a cavern floor and it ranged from 0 to 70 cm. These can provide useful information in developing necessary EDZ-related regulations for domestic disposal facilities.

• Proceedings of the Korean Nuclear Society Conference
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• 2002.10a
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• pp.330.1-330
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• 2002

• Proceedings of the Korean Nuclear Society Conference
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• 2001.10a
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• pp.270.2-270
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• 2001