Among nuclear power plants in the Republic of Korea, Kori Unit 1 and Wolsong Unit 1 have been permanently shut down, and Kori Unit 1 is preparing to be decommissioned. According to the decommissioning plan (DP) of Kori Unit 1, a radioactive waste processing complex will be built on the Kori site to reduce radioactive waste generated during decommissioning actively, and various types of decommissioning waste are expected to be treated in the complex. It is judged that matters related to the safety assessment of the complex are not included in the DP since the equipment and treatment processes have not been determined. IAEA GSR Part 5 states that radioactive waste processing complex shall be operated according to national regulations and the conditions imposed by the regulatory body. However, it has been confirmed that separate regulatory requirements for the complex have not yet been established in Korea. It is expected that the Regulation on Technical Standards for Nuclear Facilities, etc. will be applied mutatis mutandis. Liquid and gaseous radioactive materials can be expected to be released into the sea or atmosphere during the operation of the complex. Accordingly, it should be proved that standards such as discharge limits of radioactive effluents are met. Although the assessment of radioactive effluent discharged from nuclear power plants to the environment is systematically conducted, it has been confirmed that the safety assessment framework for radioactive effluents discharged from the complex has not yet been established. Currently, the SAFRAN Tool is based on SADRWMS (Safety Assessment Driving Radioactive Waste Management Solutions), an IAEA safety assessment methodology for pre-disposal management, which uses Pathway Dose Factors (PDFs) derived from generic environmental models. Therefore, in order to conduct a more detailed safety assessment of the complex on a specific site, site characteristic data should be reflected. Although safety assessment using the SAFRAN Tool was conducted at the Thailand Institute of Nuclear Technology (TINT) facility, detailed data were not provided, and PDFs reflecting site characteristic data were not applied. Also, no other studies that considered many types of waste and provided detailed data on the safety assessment were not confirmed. Therefore, this study developed K-CRAFT (Kyung Hee – Comprehensive RAdioactive waste treatment Facility safety assessment Tool), this tool that can derive PDFs by reflecting site characteristic data based on the SADRWMS methodology and conducted preliminary safety assessment for the complex which will be built in Kori site by this tool.

Over the years, in the field of safety assessment of geological disposal system, system-level models have been widely employed, primarily due to considerations of computational efficiency and convenience. However, system-level models have their limitations when it comes to phenomenologically simulating the complex processes occurring within disposal systems, particularly when attempting to account for the coupled processes in the near-field. Therefore, this study investigates a machine learning-based methodology for incorporating phenomenological insights into system-level safety assessment models without compromising computational efficiency. The machine learning application targeted the calculation of waste degradation rates and the estimation of radionuclide flux around the deposition holes. To develop machine learning models for both degradation rates and radionuclide flux, key influencing factors or input parameters need to be identified. Subsequently, process models capable of computing degradation rates and radionuclide flux will be established. To facilitate the generation of machine learning data encompassing a wide range of input parameter combinations, Latin-hypercube sampling will be applied. Based on the predefined scenarios and input parameters, the machine learning models will generate time-series data for the degradation rates and radionuclide flux. The time-series data can subsequently be applied to the system-level safety assessment model as a time table format. The methodology presented in this study is expected to contribute to the enhancement of system-level safety assessment models when applied.

The Korea Atomic Energy Research Institute (KAERI) is currently developing a process-based performance assessment model known as APro. Distinguished from the previous system-level safety assessment model developed by KAERI, APro exhibits the capacity to encompass a threedimensional biosphere domain, evolving over the long term. In this study, we elucidate the methodology employed in developing the dose assessment module of APro and present the module’s functionalities. The procedural steps underlying radiation dose calculations within the APro framework can be succinctly outlined as follows: 1) Definition of a landscape model, utilizing information derived from a specified snapshot period provided by the APro biosphere transport module; 2) Generation of unit biotope objects spanning the landscape; 3) Evaluation of radionuclide transfer within the soil medium; 4) Calculation of activity concentration for flora and fauna groups; 5) Assessment of the distribution of effective dose among representative human groups; 6) Progressing through successive time steps. The APro dose calculation module exhibits notable capabilities that encompass: 1) Accounting for radionuclide decay and ingrowth; 2) Facilitating transfer through unsaturated porous media; 3) Considering sorption effects; 4) Addressing the inheritance of radioactivity between various landscape models; 5) Offering customizable ecosystem parameters; 6) Providing flexibility for user-defined exposure pathways. Leveraging these functionalities of the dose assessment module, APro is proficient in evaluating the distribution of radiological doses and associated risks for representative population groups, all while accounting for the dynamic, long-term evolution of the biosphere, including alterations in land cover.

The Spent Nuclear Fuel (SNF) cladding serves as the first barrier that prevents the release of radioactive materials. It is very important to maintain cladding integrity in SNF management. It is known that the pinch load applied to the cladding can lead to Mode-3 failure and the cladding becomes more vulnerable to this failure mode with the existence of radial hydrides and other forms of mechanical defects. In this study, a numerical analysis process was proposed to scientifically and systematically evaluate the fracture resistance of cladding with reoriented hydrides under pinch load. The mechanical behavior and fracture of the irradiated cladding under pinch load can be evaluated by Ring Compression Test (RCT). Under the stress field generated by RCT, the cracks propagate more easily through radial hydrides than circumferential hydrides. The δ-hydride which form within the α-zirconium matrix causes a large expansion strain due to the volume difference and voids form at the interface between the hydride and the zirconium matrix. Chan demonstrated that the load needed to form voids and separate the hard hydride precipitates from the Zr matrix is considerably lower than that which initiates brittle fracture of hydrides using a micro-cantilever test. Therefore, we propose a microstructure crack propagation analysis method based on Continuum Damage Mechanics (CDM) that can simulate fracture of hydride, zirconium matrix, and Zr/hydride interface. CDM is possible to simulate the hydride, zirconium matrix, and interface cracking in a continuum model based on cladding deformation. The RCT simulation model was constructed from the microscopic images of irradiated cladding. A pixel-based finite element model was created by separating the hydride, zirconium matrix, and interface using the image segmentation method on a morphology operation basis. The appropriate element size was selected for the efficiency of the analysis and crack propagation using CDM. The force-displacement curves and strain energy from RCT were compared and analyzed with the simulation results of different element sizes. The finalized RCT simulation model can be used to evaluate the fracture resistance of the irradiated cladding under the quantified pinch load and to establish the failure criterion of fuel rods under pinch load. The advantages and limitations of the proposed process are discussed.

Korea has signed nuclear cooperation agreements (NCA) with 29 countries. Nuclear materials, materials, equipment, and technology transferred under the agreements are “internationally controlled materials (ICM)” under the Nuclear Safety Act. The main obligations imposed on those items include ensuring peaceful use, safeguards, physical protection, annual inventory reporting, and retransfer with supplier prior consent. The Nuclear Export and Import Control System (NEPS) handles the export control procedures for transferring ICM. After import, inventory management for ICM in Korea would be transitioning to an item-based system through the Obligation Tracking System for internationally controlled item (OTS) currently under development. A one-stop import and export control system for ICM can be established when information is well-linked between these two systems. This paper aims to derive a methodology for integrating NEPS and OTS. NEPS-OTS coupling begins at the receipt confirmation and shipment notification stages in NEPS. When importing ICM under NCA, the inventory change (code RF: receipt foreign) is entered in OTS by getting the information that has completed the receipt confirmation in NEPS. Conversely, during export, the information that has completed the shipment notification procedure in NEPS is linked to the OTS so that the entire cycle from import to re-export of the ICM can be concluded. Inventory verification for retransfer, checking that the book inventory remains positive value, is impossible under the current system. This issue can be resolved by enabling inventory information in OTS to be displayed in NEPS. Determining when and how to generate the obligation code for imported ICM is essential for NEPS-OTS coupling. Manual input may be necessary for some cases with multiple obligations. Nevertheless, it is more efficient from a system communication protocol to automatically generate and impose a single obligation based on the supplier country information in NEPS. Moreover, it is important to automatically link crucial information available in NEPS to reduce the administrative burden on OTS users and discrepancies between systems. Most required OTS data, such as country obligation, item categories, quantity, physical or chemical form, and receipt date, can be directly linked from NEPS. However, NEPS improvement is needed for digitizing the receiver information and facility data, like the material balance area. The NEPS-OTS integration involves sharing data as a system and encompasses the connection between export control and inventory management. Future work to link some information in NEPS -OTS with the KSIS could be suggested to enhance efficiency and effectiveness in managing ICM.

프로바이오틱스 제품에 대한 수요가 지속적으로 증가하 고 있으며, Lactobacillus 균주가 가장 대중적인 프로바이 오틱스로 널리 사용되고 있다. 프로바이오틱스는 기준에 적합한 균수의 확보가 중요하며 제조원가나 시간 등을 낮 추기 위해 배양법의 개발이 필요하므로 Lactobacillus 생 산을 위한 배양 조건이 최적화되었다. 반응표면방법론에 의한 통계적 최적화에서 반응 변수에 영향을 미치는 독립 변수의 최적 조건은 Lactobacillus acidophilus의 경우 22.55 시간(배양시간), 25oC(배양온도), 3.41%(프리바이오틱스 농 도); Lactiplantibacillus plantarum의 경우 24시간, 30.86oC, 2.00%; Lacticaseibacillus rhamnosus의 경우 66.67시간, 35oC, 3.41%이었다. Lactobacillus의 최적 배양조건은 예측 한 결과와 실제 결과가 밀접하게 일치하는 것을 확인하였 다. 이러한 데이터는 수율 높은 Lactobacillus를 생산하는 데 중요한 포인트를 제공할 것이다.

한국의 초고령화 사회에서 노인일자리전담기관인 시니어클럽은 지역사회 에서 어떠한 기능을 발휘할 수 있으며, 그 정체성을 어떻게 정의할 수 있을까? 본 연구는 시니어클럽의 기능에 관한 이해당사자들의 주관적 인식을 분석하여 이 질문에 대한 해답을 탐색하고자 하였다. 연구방법 으로 주관성을 연구대상으로 다루는 Q방법론을 적용하였다. Q모집단은 시니어클럽에 대한 다양한 인식으로 개별 및 집단인터뷰를 통해 수집 하였고, Q표본에는 37개의 진술문이 채택되었다. P표본으로는 시니어 클럽 종사자, 참여노인, 예비참여노인(지역주민) 총 25명이 연구에 참여 하였다. PQ Method 프로그램을 활용해 자료분석한 결과, 시니어 클럽의 기능에 대한 인식은 3개 유형으로 도출되었다. 1유형은 일자리개발 기관, 2유형은 직무교육 및 일자리 제공기관, 3유형은 노동권익 보호기관으로 나타났다. 이러한 분석결과를 토대로 시니어클럽이 지역사회에서 그 역할을 공고히 하기 위해 어떠한 정책적, 행정적, 실천적 노력이 필요한지 몇 가지 함의를 제안하였다.

PURPOSES : The purpose of this study is to derive dropout rates according to various international roughness index (IRI) specifications using ProVAL, develop a comparative methodology, and indirectly assess the level of road management in each country. METHODS : Based on a literature review, the IRI specifications for each country were collected, and the ProVAL analysis tool was used to compare and analyze dropout rates according to each specification. Thus, the dropout rate rankings for each country were calculated. Additionally, by analyzing the correlation between dropout rates according to each threshold, a model was created to convert the threshold between the most commonly used baseline distances of 100 m and 161 m. RESULTS : Dropout rates were derived according to the standards of each country and rankings were assigned. Comparing 51 standards, the IRI level of New Mexico appeared to be the highest, whereas the domestic specifications ranked 36th. A model was created to convert the threshold between the standard distances of 100 m and 161 m. CONCLUSIONS : This study objectively assessed the roughness standards in various countries using the dropout rate and IRI ranking specifications. The highest specification was found for the asphalt of New Mexico in the USA, with the domestic specification ranking 36th. A model that converts the thresholds between the most commonly used baseline distances of 100 m and 161 m was developed, with slight differences across sections. For a precise conversion, individual models may be required for each section.

HNS(Hazardous and Noxious Substances)는 해양환경에 유입될 경우 인간 및 해양생물에게 해를 끼치거나, 해양시설에 부식 등의 손상을 입히거나 기타 해역의 이용을 방해할 수 있다. HNS의 규제나 관리를 위해서는 과학적인 방법을 통하여 우선순위 대상의 선정이 필요하며 이러한 방법론으로 CRS(Chemical Ranking and Scoring)기법이 전세계적으로 개발되어 사용되고 있다. 본 연구에서는 해양산업시 설로부터 해양환경으로 배출되는 HNS의 체계적 관리를 목적으로 국내외 CRS 체계를 비교 분석하였으며, 이를 통하여 우선순위 선정 도 출체계를 확립하고 연구대상 지역 및 대상시설을 선정하고 우선순위 선정체계 주요인자를 도출하였다. 또한 주요인자별 세부인자 및 정 량적 배점체계를 구축하였다. 주요인자는 각각 사회적 관심과 이슈(20점), 물질거동(10점), 노출가능성(30점), 독성(35점), 해양이용에의 영 향(5점)을 상대적으로 부여하였으며, 독성과 물질거동 세부인자의 곱을 통하여 100점만점으로 환산가능하도록 적용하였으며, 불확실성점 수(Uncertainty score)와 불확실성 비율(Uncertainty ratio)와 혼합물에 대한 고려방안을 제시하였다. 본 연구결과는 해양산업시설로부터 배출/ 유출되는 HNS 관리를 위하여 우선순위 선정시 활용될 수 있을 것으로 기대된다.

본 논문은 직류전동기(DC motor)와 전기적인 특성은 유사하지만, 수명과 신뢰성이 향상된 BLDC 모터의 제어기법에 대해 언 급하고 있다. BLDC모터는 회전자의 위치 정보를 사용하여 직류전동기의 기계적인 접촉에 의한 정류 장치를 제거함으로써 내구성과 속도 안정성을 향상시킬 수 있다. 본 연구에서는 BLDC모터의 권선에 흐르는 전류가 직류전동기의 전기자에 흐르는 구형파 형태의 전 류인 것에 착안하여 직류전동기에 대한 제어기를 설계하고, 설계된 제어기를 3상 BLDC모터에 적용하여 제어기의 유효성을 확인하였 다. 이를 위해 3상 BLDC모터의 전기적인 파라미터 값을 가지는 단상 직류전동기의 모델링을 실시하였고, 도출된 시스템에 대해 근궤 적법을 적용하여 전동기의 속도제어를 위한 PI 제어기를 설계하였다. DC 전동기의 속도제어 시뮬레이션을 시행하여 제어기의 성능을 확인하였고, 동일한 제어기를 MATLAB으로 구현한 3상 BLDC모터의 속도제어에 적용하였다. DC 전동기와 유사한 제어 결과를 3상 BLDC모터에서 얻을 수 있었고, 이를 통해 연구에서 제안한 제어기법의 유용성을 확인할 수 있었다.

The current study presents a methodology of teaching the connotations and nuances of the word Han (恨) to English-speaking Korean language learners. Since Han (恨) expresses unique and traditional aspects of Korean sensibilities, the goal would be for native English speakers to be able to understand the complexities of its meaning, in spite of the differences in culture background. To this end, research was done into how Han (恨) is translated into English, as there is no term in English with the same meaning. From these findings, a list of Korean vocabulary related to the meaning of Han (恨) was made to show its definitions in English. In addition, a survey was conducted on 42 Americans to find out how English speakers understand Han (恨). As a result of this research, the current study demonstrates the need to teach the meaning of Han (恨) to Korean language learners from English-speaking countries, and suggests a teaching methodology which follows the order of Pre-Class, In-Class and After-Class study based on the Flip-Learning model.

강진에 대한 다양한 비선형 거동을 하는 부재요소들로 이루어진 교량시스템의 현재까지의 일반적인 지진취약도 평가방법은 부재- 수준에서 평가하는 것이다. 본 연구의 목적 부재-수준의 지진취약도 평가결과로부터 구조시스템을 대표하는 시스템-수준의 지진취 약도 평가방법을 개발하는 것이다. 교량의 지진 거동을 일반적으로 교축방향과 교축직각방향으로 구분하기 때문에 본 연구에서도 시 스템-수준 지진취약도를 두 방향에 대하여 구분해 평가하였다. 길이 방향에 대한 부재-수준의 지진취약도평가는 교각, 교량받침, 충 돌, 교대, 낙교에 대하여 수행하였다. 교축직각 방향에 대해서는 충돌, 교대, 낙교의 손상이 영향을 주지 않으므로 부재-수준의 지진취 약도평가는 교각과 교량받침에 대하여만 수행하였다. 다양한 구조부재의 비선형모델을 이용한 지진해석은 OpenSEES 프로그램을 사용하여 수행하였다. 시스템-수준의 지진취약도는 부재-수준 사이의 손상이 직렬연결이라고 가정하고 평가하였다. 교각의 손상이 다른 부재-수준의 손상보다 시스템-수준의 지진취약도에 지배적인 영향을 주는 것을 알 수 있었다. 다시 말하면 가장 취약한 부재-수 준의 지진취약도가 시스템-수준의 지진취약도에 가장 지배적인 영향을 주는 것을 의미한다.

Gate valves are hydraulic components used to shut-off the water flow in water distribution systems. Gate valves may fail owing to various aspects such as leakage through seats, wearing of packing, and corrosion. Because it is considerably challenging to detect valve malfunctioning until the operator identifies a significant fault, failure of the gate valve may lead to a severe accident event associated with water distribution systems. In this study, we proposed a methodology to diagnose the faults of gate valves. To measure the pressure difference across a gate valve, two pressure transducers were installed before and after the gate valve in a pilot-scaled water distribution system. The obtained time-series pressure difference data were analyzed using a machine learning algorithm to diagnose faults. The validation of whether the flow rate of the pipeline can be predicted based on the pressure difference between the upstream and downstream sides of the valve was also performed.

Nanofillers, by virtue of their minute size, when incorporated inside a matrix, have the capability to enhance the physical parameters of the complex matrix. Graphene, the wonder material of the twenty-first century, has established itself in the field of nanofillers. However, it still has yet to find its way into the mining industry. This review paper focuses on a novel way of attaining sustainability in mining methodology using graphene as a nanofiller. The implementations can be subdivided into three categories based on their impact—economic, environment, and safety. To achieve economic welfare in mine methodology; Graphene is used to enhance the productivity of machinery. Electric-Heavy Earth Moving Machinery using LiFePO4/Graphene hybrid cathode battery is not only an ideal replacement to fossil-powered vehicles considering the contribution of environmental strain but also a more-efficient model than Electric-Heavy Earth Moving Machinery using conventional Lithium Ion Phosphate Battery batteries. Heavy Earth Moving Machinery having tires of Styrene-Butadiene Rubber/Graphene composite would have better efficacy and longer life cycle than the conventional ones. Graphene derivative Magnetic Graphene Oxide is used to achieve environmental welfare by its implication as an additive in the effluent treatment plant for its capability of removing heavy metal ions and negative-strain bacteria from the mine water. To improve the safety standards of the mine workers, graphene and its derivatives have environmental implications to constitute a safer surrounding concerning precarious situations due to the unpredictable behavior of geomaterials. Graphene can assist in constituting a more economical and reliable slope model as incorporating graphene induces restructuration and improvement in strength parameters. This enables a miner to extract more minerals in tranquility from the resources as there is an increase in compaction and shear strength. A combination of a graphene sheet and auxetic graphene foam can be placed over the blast holes to not only restrict the trajectory of the fly rocks but also attenuate some part of the explosive energy. The objective of this coagulation is to upgrade the traditional practice by replacing the conventional products, and the effect is observed in the form of achieving sustainability in the mine.

As nuclear power plants are operated in Korea, low and intermediate-level radioactive wastes and spent nuclear fuels are continuously generated. Due to the increase in the amount of radioactive waste generated, the demand for transportation of radioactive wastes in Korea is increasing. This can have radiological effect for public and worker, risk assessment for radioactive waste transportation should be preceded. Especially, if the radionuclides release in the ocean because of ship sinking accident, it can cause internal exposure by ingestion of aquatic foods. Thus, it is necessary to analyze process of internal exposure due to ingestion. The object of this study is to analyze internal exposure by ingestion of aquatic foods. In this study, we analyzed the process and the evaluation methodology of internal exposure caused by aquatic foods ingestion in MARINRAD, a risk assessment code for marine transport sinking accidents developed by the Sandia National Laboratory (SNL). To calculate the ingestion internal exposure dose, the ingestion concentrations of radionuclides caused by the food chain are calculated first. For this purpose, MARINRAD divide the food chain into three stages; prey, primary predator, and secondary predator. Marine species in each food chain are not specific but general to accommodate a wide variety of global consumer groups. The ingestion concentrations of radionuclides are expressed as an ingestion concentration factors. In the case of prey, the ingestion concentration factors apply the value derived from biological experiments. The predator's ingestion concentration factors are calculated by considering factors such as fraction of nuclide absorbed in gut, ingestion rate, etc. When calculating the ingestion internal exposure dose, the previously calculated ingestion concentration factor, consumption of aquatic food, and dose conversion factor for ingestion are considered. MARINRAD assume that humans consume all marine species presented in the food chain. Marine species consumption is assumed approximate and conservative values for generality. In the internal exposure evaluation by aquatic foods ingestion in this study, the ingestion concetration factor considering the food chain, the fraction of nuclide absorbed in predator’s gut, ingestion rate of predator, etc. were considered as influencing factors. In order to evaluate the risk of maritime transportation reflecting domestic characteristics, factors such as domestic food chains and ingestion rate should be considered. The result of this study can be used as basis for risk assessment for maritime transportation in Korea.

KHNP’s vitrification technology introduced a commercialized vitrification facility to the Hanul nuclear power site after a commercialization test through a lab test and a pilot plant at KHNP-CRI. France’s ANADEC (consortium with CEA, Orano, ECM Technologies and Andra) conducted a feasibility evaluation from FY2018 to FY2021 to apply In-Can vitrification, which was developed to treat Fukushima Effluent Treatment Waste (FETW) such as carbonate slurry and ferric slurry generated from ALPS (Advanced Liquid Processing System-Multi Radionuclides Removal) facilities for waste treatment in Fukushima, Japan. For commercialization, the following method was used. First, through the Laboratory scale studies, the possibility of high waste loading (60wt% in dry mass) of slurry on borosilicate matrix was tested. In addition, the volatility of radionuclide was evaluated through radionuclides surrogates with a Bench-scale mockup and glass discharge (100 kg) was evaluated through In-Can vitrification process verification. The feeding system was improved through a pilot scale test, and finally, glass discharge (300 kg) was evaluated after large amount of waste was treated through an industrial prototype (Fullscale) at the CEA Marcoule site (France).

Kori Unit 1 was permanently shut down in 2017 and is preparing to be dismantled. Decommissioning nuclear power plants is expected to generate a lot of decommissioning waste. Therefore, a radioactive waste treatment complex will be built on the site to safely and effectively the process of decommissioning waste generated from the Kori Unit 1, and the details are specified in the decommissioning plan. Therefore, a safety assessment should be conducted according to the facility’s normal and abnormal operations to construct a radioactive waste treatment complex. Currently, a safety assessment for a radioactive waste treatment complex can be conducted by the Safety Assessment Framework (SAFRAN) Tool based on the Safety Assessment Driving Radioactive Waste Management Solutions (SADRWMS) methodology developed by the International Atomic Energy Agency (IAEA). The SAFRAN Tool can be calculated radiation dose and hazard quotient (HQ) for workers and the public under normal and abnormal conditions of the radioactive waste treatment complex. When evaluating the radiation dose for the public due to releasing radioactive materials into the air or discharging radioactive materials into liquids, the radiation dose is calculated using the amount discharged or released from the treatment complex, and the Pathway Dose Factors (PDFs) derived from the generic environmental model given in the IAEA Safety Reports Series No.19. PDFs, which reflect the specific site data rather than the generic environmental model data, should be calculated and evaluated when performing the safety evaluation of the radioactive waste treatment complex to be built on the Kori site. In addition, in the SAFRAN tool, there is an inconvenience in that it must be calculated separately by radionuclides to calculate the contribution of dose or HQ for each radionuclide. Therefore, in this study, a safety assessment tool for a radioactive waste treatment complex was developed using Visual Basic by supplementing the limitations of the SAFRAN tool. This tool was developed to allow users to choose whether to apply PDFs based on the IAEA SRS-19 based on the generic environmental model or PDFs calculated to reflect the specific site data. Furthermore, the tool considered all types of decommissioning wastes that may occur during the decommissioning of the Kori Unit 1 and the treatment process scheduled to be introduced. Therefore, this study is expected to be used as basic data when conducting the safety assessment of radioactive waste treatment complex scheduled to be introduced in Korea.

To prevent the release of radionuclides into the biosphere, disposal facilities for radioactive waste should be located to provide isolation from the accessible biosphere for tens of thousands to a million years after closure. During the period of interest, the constantly evolving natural environment and possible geological events of the site can cause disturbances to the containment function of the repository. Thus, for the long-term safety assessment of the repository, the possible long-term change of natural barrier should be considered. Due to the characteristics of radionuclides that transport mainly through the groundwater, understanding the long-term evolution of groundwater flow and geochemical properties is essential to assess the long-term changes in the natural barrier performance. The changes in characteristics of natural rocks and geological structures are one of the main factors that determine the hydrological and geochemical characteristics of the deep underground. In this study, we plan to develop a methodology to estimate these future geological evolutions in order to assess the possibility of hazardous events of the site that can affect hydrological or geochemical properties over the period of interest, and also in order to verify the change in the geological environment is within the safe performance range even after the period of interest. However, it is very unreliable to predict future changes in the natural environment because it is very heterogeneous, complex, and difficult to observe directly. For the preliminary study of the project, we reviewed cases of future evolution prediction researches with regard to the geological environment of disposal site and methods they applied to reduce the uncertainty of the prediction. The results will be used to establish basic data for future studies on the long-term evolution of hydraulic-mechanics performance of natural barrier and long-term evolution of geochemical performance around KURT site. In addition, it can contribute to construct long-term evolution scenario of the geological environment around future URL site.