• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2018년도 추계학술논문요약집
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• pp.247-248
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• 2018

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2018년도 춘계학술논문요약집
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• pp.133-134
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• 2018

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2017년도 춘계학술논문요약집
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• pp.203-204
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• 2017

• 한국지하수토양환경학회지:지하수토양환경
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• 제20권2호
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• pp.10-21
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• 2015

The present study introduces a novel numerical approach for solving dispersion dominated problems with Cauchy boundary condition in an Eulerian-Lagrangian scheme. The study reveals the incapability of traditional Neuman approach to address the dispersion dominated problems with Cauchy boundary condition, even though it can produce reliable solution in the advection dominated regime. Also, the proposed numerical approach is applied to a real field problem of radioactive contaminant migration from radioactive waste repository which is a major current waste management issue. The performance of the proposed numerical approach is evaluated by comparing the results with numerical solutions of traditional FDM (Finite Difference Method), Neuman approach, and the analytical solution. The results show that the proposed numerical approach yields better and reliable solution for dispersion dominated regime, specifically for Peclet Numbers of less than 0.1. The proposed numerical approach is validated by applying to a real field problem of radioactive contaminant migration from radioactive waste repository of varying Peclet Number from 0.003 to 34.5. The numerical results of Neuman approach overestimates the concentration value with an order of 100 than the proposed approach during the assessment of radioactive contaminant transport from nuclear waste repository. The overestimation of concentration value could be due to the assumption that dispersion is negligible. Also our application problem confirms the existence of real field situation with advection dominated condition and dispersion dominated condition simultaneously as well as the significance or advantage of the proposed approach in the real field problem.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2008년도 학술논문요약집
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• pp.159-160
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• 2008

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2010년도 추계 학술논문요약집
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• pp.161-162
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• 2010

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2018년도 추계학술논문요약집
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• pp.565-566
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• 2018

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2003년도 가을 학술논문집
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• pp.261-265
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• 2003

현행 중ㆍ저준위방사성폐기물 인도규정의 개정에 초점을 맞추어 국내 천층처분시설에 대한 폐기물 수용요건의 개발 및 이행 방안을 제시한다. 개정안은 방사성폐기물 세부분류, 표층처분 방사능농도제한, 핵종 inventory 평가 등에 관한 구체적인 기준을 담고 있으며, 그 이행을 위하여 처분전 폐기물관리, 처분시설 안전성평가, 처분시스템 등과의 합리적인 연계를 모색한다.

• 방사성폐기물학회지
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• 제20권4호
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• pp.469-488
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• 2022

Technology for high-level-waste disposal employing a multibarrier concept using engineered and natural barrier in stable bedrock at 300-1,000 m depth is being commercialized as a safe, long-term isolation method for high-level waste, including spent nuclear fuel. Managing heat generated from waste is important for improving disposal efficiency; thus, research on efficient heat management is required. In this study, thermal management methods to maximize disposal efficiency in terms of the disposal area required were developed. They efficiently use the land in an environment, such as Korea, where the land area is small and the amount of waste is large. The thermal effects of engineered barriers and natural barriers in a high-level waste disposal repository were analyzed. The research status of thermal management for the main bedrocks of the repository, such as crystalline, clay, salt, and other rocks, were reviewed. Based on a characteristics analysis of various heat management approaches, the spent nuclear fuel cooling time, buffer bentonite thermal conductivity, and disposal container size were chosen as efficient heat management methods applicable in Korea. For each method, thermal analyses of the disposal repository were performed. Based on the results, the disposal efficiency was evaluated preliminarily. Necessary future research is suggested.

• 한국시스템다이내믹스연구
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• 제10권2호
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• pp.29-52
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• 2009

This paper reveals the conceptual relation between High Level Radioactive Waste Repository Site(HLRWR) and Policy Acceptance of Local Residents thorough the Causal Loop Diagram. The Resident's policy acceptance depends on the perceived risk of that facility. To reduce the risks, government has to prepare the schemes of the total supporting program including cash and the local development programs.