• Proceedings of the Korean Nuclear Society Conference
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• 1995.05b
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• pp.775-780
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• 1995

방사성폐기물 처분장 폐쇄후 처분시설의 성능평가를 수행하기 위해 해안에 위치한 임의의 지역을 가정하여 평가하여 보았다. 성능평가를 위해 영국 AEA Technology가 개발한 확률론적 종합 성능평가 코드인 MASCOT을 이용하였다. 임해지역에 위치한 가상 처분장에 대해 MASCOT을 이용하여 계산하여 본 결과 생태계에서 개인이 받게되는 예상 최대 위험확률은 폐쇄후 4,000년에 9.45$\times$$10^{-7}$yr$^{-1}$로서 이는 성능목표치를 만족할 수 있음을 알 수 있었다. 가상 처분장에 대해 성능평가를 수행함으로써 향후 방사성폐기물 처분부지가 결정되었을 경우, 결정된 처분부지의 특성에 따른 성능평가 및 환경영향평가를 원활히 수행할 수 있을 것이다.

• Nuclear Engineering and Technology
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• v.26 no.4
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• pp.578-599
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• 1994

방사성 폐기물 처분장의 건설에 가장 중요한 부분중의 하나는 처분안전성의 확보일 것이다. 처분장 안전성평가는 처분장이 입지하는 환경에 대한 실험실적 자료 또는 현장 자료의 충분한 데이타베이스와 처분시스템에서 일어날 수 있는 주요한 프로세스를 기술하는 수학적 모델을 통하여 이루어지게 된다. 처분시스템의 기본적인 기능은 처분된 폐기물고화체를 인간환경으로 부터 완벽하게 고립시켜 처분장내에 영구적으로 격리시키는 것이다. 그렇지만 정상적이든 비정상적이든 핵종은 항상 유출될 가능성이 있고 설사 이러한 경우라도 충분히 안전한 것을 입증하는 것이 처분장 성능 평가와 안전성평가의 주요한 목적이 된다. 한편 장기간에 걸친 처분 안전성 평가는 전산 프로그램을 통한 이론적 예측에 의해서만 가능하므로, 처분안전성 평가도구의 개발 및 확보의 중요성은 매우 크다고 할 수 있다. 이 연구에서는 처분장이 입지하는 암반 매질에서의 핵종의 이동을 기술할 수 있는 여러 모델을 검토하고, 특정 처분부지에 대한 종합적 안전성 평가를 수행할 수 있는 방법론을 제시할 목적으로 임의의 1개 부지의 지형도및 추정가능한 지질관련 자료를 이용하여 해당 부지에 대한 가상의 핵종 유출 시나리오를 설정하여 부지특성적인 예비 종합 안전성 평가를 수행하여 보았다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.10 no.3
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• pp.133-141
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• 2012

The impacts influenced on the performance and safety of a repository are classified as units of Features, Events, and Processes (FEP), for the total system performance assessment (TSPA) related to the permanent disposal of HLW. The importance is evaluated in consideration of the frequency, consequence, regulation, suitability of a specific site, etc. and then these are grouped as a similar FEP. A scenario describing the migration of radionuclide from the repository to the biosphere is derived from understanding the interaction among these groups. KAERI has developed the KAERI FEP lists by review and collation of the foreign studies. The KAERI FEP list has been reviewed by several Korean experts. The five major scenarios describing possible future evolutions of the geological disposal system have been developed by RES and PID methods. Also the CYPRUS which is a KAERI integrated database management system for the total system performance assessment (TSPA) related to the permanent disposal of HLW has been developed and the results of the FEP and scenario development have been uploaded in this system.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.189-192
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• 2004

본 연구에서는 한국형 중저준위 방사성폐기물 처분시설 안전성 평가를 위한 FEP 목록 도출 방법 및 선별 원칙들을 제시하였으며, 처분장에서의 핵종 이동 시나리오에 대해서는 생태계의 특성 및 공학방벽에 따라 각각의 RES (Rock Engineering System)를 구성하여 각 상황별 핵종이동을 모사 할 수 있도록 제안하였다. 또한 각 시나리오별 안전성 평가를 위하여 적용 가능한 해석 코드를 제안하였으며, 종합 성능 평가를 위한 보완점을 지적하였다. 추후 종합 성능 평가 시스템을 통해 최종적으로 도출될 안전성 평가 결과는 한국형 처분장 설계시에 활용될 수 있을 것으로 기대된다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.4 no.1
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• pp.65-75
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• 2006

Transparency on the Total System Performance Assessment (TSPA) is the key issue to enhance the public acceptance for a radioactive repository. To approve it, all performances on TSPA through Quality Assurance is necessary. The integrated Cyber R&D Platform is developed by KAERI using the T2R3 principles applicable for five major steps : planning, research work, documentation, and internal & external audits in R&D's. The proposed system is implemented in the web-based system so that all participants in TSPA are able to access the system. It is composed of three sub-systems; FEAS (FEp to Assessment through Scenario development) showing systematic approach from the FEPs to Assessment methods flow chart, PAID (Performance Assessment Input Databases) being designed to easily search and review field data for TSPA and QA system containing the administrative system for QA on five key steps in R&D's in addition to approval and disapproval processes, corrective actions, and permanent record keeping. All information being recorded in QA system through T2R3 principles is integrated into Cyber R&D Platform so that every data in the system can be checked whenever necessary. Throughout the next phase R&D, Cyber R&D Platform will be connected with the assessment tool for TSPA so that it will be expected to search the whole information in one unified system.

• Tunnel and Underground Space
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• v.10 no.4
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• pp.553-558
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• 2000

Since 1977, KAERI has conducted the fundamental R&D on the permanent disposal of potential HLW repository in Korea. The first ten year project is divided into three short-term phase studies. The first phase study which shall be finished in March of 2000, has the prime target to develop the disposal concept of HLW. Throughout this study the preliminary and generic disposal repository system has been introduced. The potential repository is proposed to be emplaced into crystalline rocks which is the most common rock types in Korea. The proposed depth of the repository is between 300 to 700 meter. The numerical code, MASCOT-K was developed to asserts the long term safety of the proposed repository concept. Based on this conceptual design preliminary safely assessment was performed. Results show that for the given disposal system the potential radioactive release it well below the regulatory limit.

• The Journal of Engineering Geology
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• v.33 no.4
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• pp.725-736
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• 2023

The compliance of deep geological disposal facilities for high-level radioactive waste with safety objectives requires consideration of uncertainties owing to temporal changes in the disposal system. A comprehensive review and analysis of the characteristics of this evolution should be undertaken to identify the effects on multiple barriers and the biosphere. We analyzed the evolution of the buffer, backfill, plug, and closure regions during the early phase of the post-closure period as part of a long-term performance assessment for an operating license application for a deep geological repository in Finland. Degradation mechanisms generally expected in engineered barriers were considered, and long-term evolution features were examined for use in performance assessments. The importance of evolution features was classified into six categories based on the design of the Finnish case. Results are expected to be useful as a technical basis for performance and safety assessment in developing the Korean deep geological disposal system for high-level radioactive waste. However, for a more detailed review and evaluation of each feature, it is necessary to obtain data for the final disposal site and facility-specific design, and to assess its impact in advance.

• Tunnel and Underground Space
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• v.13 no.4
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• pp.270-278
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• 2003

Transparency on the Total System Performance Assessment (TSPA) is the key issue to enhance the public acceptance for a permanent high level radioactive repository. Traditionally, the study on features, events and processes (FEPs) and associated scenarios has been regarded as the starting point to open the communicative discussion on TSPA such as what to evaluate, how to evaluate and how to translate outcomes into more friendly language that many stakeholders can easily understand and react with. However, in most cases, it has been limited to one way communication, because it is difficult for stakeholders outside the performance assessment field to assess the details on the story of the safety assessment, scenario and technical background of it. Fortunately, the advent of the internet era opens up the possibility of two way communication from the beginning of the performance assessment so that every stakeholder can exchange their keen opinions on the safety issues. To achieve it, KAERI develops the systematic approach from the FEPs to Assessment methods flow chart. All information is integrated into the web based program named FEAS (FEp to Assessment through Scenario development) under development in KAERI. In parallel, two independent systems are also under development the web based QA(Quality Assurance) system and the PA(Performance Assessment) input database. It is ideal to integrate the input data base with the QA system so that every data in the system can checked whenever necessary. Throughout the next phase R&D starting from the year 2003, these three systems will be consolidated into one unified system.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.17 no.2
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• pp.227-234
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• 2019

A user-friendly modeling interface is developed for a process-based total system performance assessment framework (APro) specialized for a generic geological disposal system for high-level radioactive waste. The APro modeling interface is constructed using MATLAB, and the operator splitting scheme is used to combine COMSOL for simulation of multiphysics and PHREEQC for the calculation of geochemical reactions. As APro limits the modeling domain to the generic disposal system, the degree of freedom of the model is low. In contrast, the user-friendliness of the model is improved. Thermal, hydraulic, mechanical and chemical processes considered in the disposal system are modularized, and users can select one of multiple modules: "Default process" and multi "Alternative process". APro mainly consists of an input data part and calculation execution part. The input data are prepared in a single EXCEL file with a given format, and the calculation part is coded using MATLAB. The final results of the calculation are created as an independent COMSOL file for further analysis.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.14 no.4
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• pp.385-410
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• 2016

The disposal facility in Gyeongju is planning to dispose of 800,000 packages of low- and intermediate- level radioactive waste. This facility will be developed as a complex disposal facility that has various types of disposal facilities and accompanying management. In this study, based on the comprehensive development plan of the disposal facility, a preliminary post-closure safety assessment is performed to predict the phase development of the total capacity for the 800,000 packages to be disposed of at the site. The results for each scenario meet the performance target of the disposal facility. The assessment revealed that there is a significant impact of the inventory of intermediate-level radionuclide waste on the safety evaluation. Due to this finding, we introduce a disposal limit value for intermediate-level radioactive waste. With stepwise development of safety case, this development plan will increase the safety of disposal facilities by reducing uncertainties within the future development of the underground silo disposal facilities.