Decommissioning of Nuclear Power Plant (NPP) projects in South Korea starts with permanent shutdown of Kori unit 1 and Wolsung unit 1. It is important to establish a treatment and disposal method for radioactive waste generated during the decommissioning of the nuclear power plants. Large quantities of the wastes during decommissioning of NPP are generated in a short period of time and the wastes have various types and characteristics. For efficient decommissioning of NPP process, the radioactive waste is classified by types and each treatment method and packaging concept is presented respectively in this paper. Radioactive waste generated during decommissioning of NPP is classified into reactor vessel, reactor internals, metals, Dry Active Waste (DAW), concreate, spent fuel storage rack, spent resin and spent filter, etc., and the packaging concept for each type should be established to meet the waste acceptance criteria. Major waste acceptance criteria requirements include nuclides concentration, filling rate, free water, surface radiation does rate and weight. Radioactive waste containers can be classified into packaging containers, transport containers, and disposal containers. The packaging container is used to contain, transport, and store radioactive waste within the radiation control area, and a control number has been assigned as a radioactive waste drum after the final treatment has been completed. The transport container is used for transporting radioactive waste filled-containers from a radiation control area through an uncontrolled area. In this paper, the concept of disposal of dismantled radioactive waste and packaging methods were reviewed in comprehensive consideration of domestic radioactive waste transport and storage regulations, permanent disposal environment, and development status of large containers.

For the performance analysis of deep geological repository systems, numerical simulation with multi-physics is required, which specifically covers Thermal (T), Hydraulic (H), and Mechanical (M) behaviors in the disposal environment. Numerous simulation models have been developed so far, each of which varies in the approach and methodology for solving THM problems. Fully-coupled THM simulation codes such as ROCMAS, THAMES, and CODE_BRIGHT were mainly developed in the initial stage of DEvelopment of COupled models and their VALidation against EXperiments (DECOVALEX), with the advantage of thorough calculations consisting of correlated several variables on different physics. Due to the difficulty of solving the complex Jacobian Matrix and the following burden for the computational calculation, weakly-coupled THM models have been suggested in recent researches: TOUGH2-MP with FLAC3D, TOUGH2 with UDEC and OpenGeoSys with FLAC3D. This methodology of loose coupling allows the practical use of computational code optimized for each physics, thereby increasing the efficiency in simulation. However, these suggested models require two different numerical codes to calculate THM behaviors, which leads to several inherent issues: compatibility during maintenance, updating and dependency between two codes. In this study, therefore, the authors build a unified code for simulating THM behaviors in the deep geological repository. The concept involves the iterative sequential coupling between TH and M for calculation efficiency. As having developed the simulation code, High-level rAdiowaste Disposal Evaluation System (HADES), to describe TH behavior based on Multi-physics Object-Oriented Simulation Environment (MOOSE) software, the authors make a milestone to develop and couple the MOOSE-based new code for M behavior as Sub-app, with the previous HADES set to be Main-app. New model for M behavior will be verified with the benchmark case of DECOVALEX-THMC Task D, comparing the mechanical simulation results: stress evolution over time, profiles of stress and vertical displacement. The existing simulation results from HADES will also be updated with the coupled calculations, with regard to temperature and saturation. Additionally, the effective stress evolution can be assessed in terms of repository’s stability with Spalling Strength and Mohr-Coulomb failure criterion. This concept for new simulation model has its meaning in that it aims to demonstrate the specific methodology of loosely coupling multi-physics in unified simulation code and analyze THM complex interactions with considering mutual influence on various physics. It is expected that HADES can be renewed as an integral simulation model for deep geological repository systems by possessing the capacity for analyzing and assessing mechanical behavior.

Since 1992, various numerical codes, such as TOUGH-FLAC and ROCMAS, have been developed and validated to dispose of Spent Nuclear Fuel (SNF) safely through a series of DEvelopment of COupled models and their VALidation against EXperiments (DECOVALEX) projects. These codes have been developed using different approaches, such as general two-phase flow and Richards’ flow which is an approximated approach neglecting gas pressure change, to implement the same multiphysics behaviors. However, the quantitative analysis for numerical results, which originated from different fundamental approaches, has not been conducted accurately. As a result, improper utilization of the approach to analyze certain conditions occurring such as dramatic gas pressure change may result in erroneous outcomes and systemic problem pertaining to TH analysis. In this study, the quantitative analysis of the two approaches, in terms of TH behavior, was conducted by comparing them with a 1D simulation of the CTF1 experiment carried out by laboratory experiment. The results calculated by different approaches show agreement in terms of TH behaviors and material properties change until 120°C. The results verify the applicability of Richards’ flow approach in a high temperature environment above the current thermal criteria, set as 100°C, and gas pressure change does not have a significant impact until 120°C. Therefore, although further studies for applicability of Richards’ flow are needed to suggest the appropriate temperature range, these quantitative analyses may contribute to the performance assessment of a compact repository using the high-temperature bentonite concept, which is currently gaining attention.

In order to use nuclear energy stably, high level radioactive waste including spent nuclear fuel that is inevitably discharged from nuclear power plants after electricity generation must be managed safely and isolated from the human living area for a long period of time. In consideration of the accumulated amount of spent nuclear fuel anticipated according to the national policy for HLW management, the area required for the deep geological repository facility is expected to be very large. Therefore, it is essential to conduct various studies to optimize the area required for the disposal of spent nuclear fuel in cases where the nationally available land is extremely limited, such as in Korea. In this study, as part of such research, the strategies and the requirements for the preliminary design of a high efficiency repository concept of spent nuclear fuel were established. For PWR spent nuclear fuel, seven assemblies of spent nuclear fuel can be accommodated in a disposal canister, and high burnup of spent nuclear fuel was taken into consideration, and the source terms such as the amount and time of discharge and disposal were based on the 2nd national basic plan. By evaluating the characteristics, the amount of decay heat that can be accommodated in the disposal canister was optimized through the combination of seven assemblies of spent nuclear fuel. The cooling period of the radiation source for the safety assessment of the repository system was set at 55 years, and the operation of the repository would start from 2070 and then the disposal schedule would be conducted according to the disposal scenario based on the national basic plan. With these disposal strategies described above, the main requirements for setting up the conceptual design of the high efficiency repository system to be carried out in this study were described below. • A combination of seven spent nuclear fuels with high heat and spent nuclear fuels with low heat was loaded into a disposal canister, and the thermal limit per disposal canister was 1,600 W. • In order to maintain the long-term performance of the repository, the maximum temperature design limit in the buffer material was set to 130°C. • In the deep disposal environment, the safety factor [yield strength/maximum stress] required to maintain the structural stability of the disposal canister should be maintained at 2.0 or higher so that integrity of the canister can be maintained even under long-term hydrostatic pressure and buffer swelling pressure in the deep disposal environment. • The repository should have a maximum exposure dose of 10 mSv/yr or less, which is the legal limit in case of a single event such as an earthquake, and the risk level considering natural phenomena and human intrusion, which is less than the legal limit of 10-6/yr. These strategies and requirements can be used to develop the high-efficiency geological disposal concept for spent nuclear fuels as an alternative disposal concept.

A phosphorylation (phosphate precipitation) technology of metal chlorides is considering as a proper treatment method for recovering the fission products in a spent molten salt. In KAERI’s previous precipitation tests, the powder of lithium phosphate (Li3PO4) as a precipitation agent reacted with metal chlorides in a simulated LiCl-KCl molten salt. The reaction of metal chlorides containing actinides such as uranium and rare earths with lithium phosphate in a molten salt was known as solidliquid reaction. In order to increase the precipitation reaction rate the powder of lithium phosphate dispersed by stirring thoroughly in a molten salt. As one of the recovery methods of the metal phosphates precipitated on the bottom of the molten salt vessel cutting method at the lower part of the salt ingot is considered. On the other hand, a vacuum distillation method of all the molten salt containing the metal phosphates precipitates was proposed as another recovering method. In recent study, a new method for collecting the phosphorylation reaction products into a small recovering vessel was investigated resulting in some test data by using the lithium phosphate ingot in a molten salt containing uranium and three rare earth elements (Nd, Ce, and La). The phosphorylation experiments using lithium phosphate ingots carried out to collect the metal phosphate precipitates and the test result of this new method was feasible. However, the reaction rate of test using lithium phosphate ingot is very slower than that of test using lithium phosphate powder. In this presentation, the precipitation reactor design used for phosphorylation reaction shows that the amount of molten salt transferred to the distillation unit will reduce by collecting all of the metal phosphates that will be generated using lithium phosphate powder into a small recovering vessel.

대다수의 부유식 해양플랜트는 위치 유지의 방법으로서 체인 계류 시스템을 사용하나, 그 설계 변경 과정은 논문으로 찾아보 기 힘들다. 본 연구는 FLBT를 대상 해양플랜트로 선정하여 계류 초기설계안과 모형시험을 수치해석으로 분석하고, 변경된 설계조건에 따 라 새로운 계류 설계안을 제시하였다. 주된 환경 방향에 따라 계류선 묶음(bundle)의 주 방향을 조절하는 것이 계류 설계하중 감소에 크게 유효했다. 터렛 계류된 해양플랜트라도 횡파에 노출되며, 횡파 중 운동 때문에 높은 계류 인장력이 발생했다. 일치된 환경 방향 조건은 설 계조건이 될 수 없으며, 바람, 파도, 조류의 각 환경 방향이 복잡한 조건에서 설계 계류 하중이 발생했다. 횡요 운동이 계류 인장력에 미치 는 영향이 큼으로 적절한 횡요 감쇠 계수를 계류해석에 적용하는 것이 중요하다.

본 연구의 목적은 나무그림 검사가 비행청소년의 자기개념의 반응을 평가하는 심리검사 도구로서 유용성을 알아보고자 하는 것이다. 연구대상은 광주광역시에 소재하는 직업훈련소년원 255명이며, 연구도구는 나무그림 검사와 자기개념 척도 지를 사용하였다. 자료분석은 SPSS-Win 23.0 프로그램을 사용하여 t검증을 실시하 였다. 연구결과는 다음과 같다. 첫째, 나무그림 검사의 형식적 반응특성에서 크기 와 위치 및 필압에서 유의미한 차이가 나타났다. 둘째, 나무그림 검사의 내용적 반응특성에서 줄기와 가지 및 상흔에서 유의미한 차이가 나타났다. 이러한 연구결 과를 바탕으로 나무그림 검사가 비행청소년의 자기개념 수준을 판별할 수 있는 검사도구로서 유용한지에 대하여 논의하였다.

본 연구에서는 대학생이 직업을 어떻게 선택하는지 밝히기 위하여 진로대안영역과 직업포부를 확인한 후, 자아개념과의 관계를 살펴보았다. 선정된 직업으로 구성된 질문지를 대학생에게 배부하여 총 422명의 사례가 최종 분석에 사용되었다. 수집된 자료를 바탕으로 엑셀 2019와 SPSS 22.0을 사용하여 기술 통계 치, 교차분석, 상관분석을 실시하였다. 연구 결과, 첫째, 중성적이고, 지위에 대한 인식이 높게 나타났다. 둘째, 진로대안영역의 성역할 유형 범위는 3.27점~5.01점, 지위수준은 3.67점~5.29점으로 나타났다. 셋 째, 직업포부는 422명 중 203명(48.1%)이 진로대안영역안에 위치하는 것으로 확인되었다. 넷째, 진로대 안영역의 성역할하한선과 성공욕구는 낮은 부적 관계, 지위상한선과 학업 성적, 주변의 기대, 성공욕구는 낮은 정적 관계로 나타났다. 그리고 직업포부는 지위수준과 주변의 기대, 성공욕구는 낮은 정적 관계로 나 타났다. 위 결과를 바탕으로 제언과 시사점을 논의하였다.

Purpose: This qualitative phenomenological study aims to understand how nursing students interpret their experiences with handover education using concept maps in simulation-based nursing education. Methods: Data were collected from September 18, 2021 to April 6, 2022, through in-depth one-to-one interviews with 11 nursing students. Interviews, which were conducted once or twice, lasted for 30 to 45 minutes per session. The main interview question was “How do you make meaning of your experiences with handover education using concept maps in simulation-based nursing education?” The collected data were analyzed using content analysis. Results: Three categories of were identified: actively engaged with students, addressed the reality of handover education, and there are two sides to handover education. The participants in this study require systematic education on the take-over method and process that can integrate and structure the continuity and thinking necessary for nursing work. Conclusion: Handover education using concept maps in simulation-based methods should be adapted according to the abilities of nursing students and their contextual needs. Future studies using large sample sizes and multiple settings should substantially evaluate the impact of handover education programs using concept maps on clinical outcomes.

해양법협약은 유연한 개정이 어려워 과학기술 발전에 따라 새로이 발명된 기술이나 장비, 또는 활동에 대하여 명확한 법적 근거를 제시하지 못하는 측면 이 있다. 최근에 논의되고 있는 운용해양학의 개념은 해양법협약상 해양과학조 사와 비슷한 측면이 존재하지만, 명확한 용어가 명시되어 있지 않기 때문에 해 석상 혼동이 되는 측면이 있으며, 따라서 해양법협약을 기반으로 한 운용해양 학의 개념과 적용 법리에 대한 국제사회의 의견이 나뉘고 있다. 본 논문의 목적은 운용해양학의 법적 정의를 내리고자 하는 것이 아니며, 운용해양학의 법 적 모호성으로 인해 고려될 수 있는 문제점을 식별해보고, 국내에 어떻게 영향 을 미칠 수 있는지 예측하는데 있다. 연구결과, 운용해양학은 ‘법률을 무기로서 사용한다’는 개념인 법률전에 사용될 가능성이 있으며, 추후 국제사회의 논의에 따라 해양경계획정 갈등이 있는 국가 사이에도 영향을 미칠 수 있을 것으로 보 았다. 이와 같은 상황은 우리나라와도 무관하지 않으며, 이에 첨언으로서 기초 적인 대응방안을 고찰하고자 하였다.

국제해사기구(IMO, International Maritime Organization)를 중심으로 자율운항선박 도입을 대비한 해사안전 및 보안관련 국제 협약 을 제정하고 있다. 국내에서도 선급 및 산업체를 중심으로 자율운항시스템 기술개발에 착수하고 있으며 연안선박에서 발생하는 사고를 줄이기 위해 연안선박을 대상으로 하는 자율운항선박 기술적용 방안 연구가 진행되고 있다. 국내외적으로 자율운항선박에 대한 관심이 크게 증가하고 있으며 실제 개발된 기술의 검증을 위한 해상실증이 본격적으로 추진되고 있다. 본 연구에서는 연안선박에 적용하기 위한 디지털트윈 기술 관련 실증선박과 육상 플랫폼(원격지원센터)의 설계를 위한 기초연구를 진행하였다. 디지털트윈 기술을 선박에 적용하 기 위해 8m 소형 배터리 전기추진선박을 대상으로 선정하였으며, 선박과 육상 플랫폼 간 통신을 통해 선박 항해 및 운전 데이터가 서버 시스템에 저장되고 전기추진선박의 원격제어 명령이 가능한 디지털트윈 통합 플랫폼의 기본 설계를 진행하였다. 이러한 디지털트윈 기술 을 적용한 선박 성능관리, 운항 및 운영 최적화, 예지제어 등이 가능할 것으로 판단되며, 위기상황에 대응이 가능한 안전하고 경제성 있는 디지털트윈 기술의 선박적용이 가능할 것이라 사료된다.

자율운항선박(MASS : Maritime Autonomous Surface Ships)은, 고도의 자율도를 가지고, 계획된 경로를 따라 자율 운항하지만, 필요시 육상원격제어센터(SRCC : Shore Remote Control Center)에서 선박의 운항에 직접 개입할 수 있다. 본 연구에서는 이러한 자율운항 선박의 운항을 육상에서 모니터링하고 유사시 원격제어하는 역할을 담당할 육상원격제어사(SRCO : Shore Remote Control Officer)의 교육 훈련에 필요한 시뮬레이터 시스템의 운용개념과 이를 가능하게 하기 위한 요구기능에 대해 검토하였다. 육상원격제어 시뮬레이터 시 스템은, 다수의 자율운항선박의 운항상황을 모니터링하는 Monitoring Station, 유사시 특정 선박의 운항에 직접 원격개입하는 Control Station의 기능을 모의하도록 하였고, 시뮬레이션 종합통제실, 자율운항선박 운항상황 모의 시뮬레이터, 그리고 주변의 유인선 운항을 모의하기 위한 통항선 시뮬레이터 등으로 구성하였다. 기능적으로는, 육상에서 선박을 직접 제어하기 위하여 원격으로 개입하는 ESRC(Emergency Situation for Remote Control) 상황을 정의하여 이러한 상황을 모의할 수 있도록 하였다.

Radioactive spent resin and concentrate waste powder generated from the primary system of nuclear power plants (NPPs) should be treated and disposed of in the form of solidified products or high integrity container (HIC) packages. We are preparing for the application of polymer concrete high integrity containers (PC-HICs) that has been approved for disposal and field application after going through the disposal suitability review of the repository operator and the license review process of the regulatory body. A reliable assessment of nuclide inventory in waste drum is required for the disposal of the radioactive waste drums, and the representative samples should be collected for both the indirect (non-destructive assessment based on the scaling factor, average radioactivity concentration, etc.) and direct (destructive analysis) evaluation of the difficult-to-measure (DTM) nuclides. It is important to secure the representativeness of samples for reliable and accurate evaluation of radionuclide inventory and approval of methodologies for highly radioactive waste such as spent resin and concentrate waste poser, and in order to secure the radiation safety of the sampling workers and representativeness of the samples, a remote sampling method is required with excellent convenience and safety and sufficient representativeness of the sample. The simple sampling device used in the past to collect samples for the scaling factor does not have a remote control function, so high-radiation samples must be collected within a very short time and it is difficult to obtain sufficiently representative samples due to structural characteristics that cannot collect the entire sample in the axial direction of the package. Therefore we developed concept designs for a remote sampling device that can satisfy both sample representativeness, operator convenience and safety.

The bilateral nuclear cooperation agreement provides the basis for technical and economic exchanges and research and development cooperation in the nuclear industry, while also having an important role in the peaceful use of nuclear power. The government of Republic of Korea has signed the supplementary and additional arrangements with the United States, Canada, and Australia to specify detailed procedures necessary for the implementation of the agreement. Currently, items under the bilateral nuclear cooperation agreement (i.e., obligated items) are managed through official documents and e-mails, and it is difficult for the government to systemically track item inventory and identify the person in charge. Another issue is the discrepancy of information between the annual report on obligated items and the report under the import and export procedure. In order to solve these problems, the government is establishing an import and export management system for obligated items to enhance transparency and national reliability in Korea. The ultimate purpose of this project is to not only faithfully fulfill the obligations under the bilateral nuclear cooperation agreement, but also to increase the efficiency of implementation work through systematization of databases and management of obligated items. In this paper, an improved management procedures are suggested by analyzing the required functions and problems. Also, this paper provides a conceptual design that can be applied to the management system for it obligated items by identifying and analyzing practical problems in the import and export management of mandatory items. As a result, key considerations and the conceptual design proposal for the ‘export and import management system for items subject to the nuclear bilateral cooperation agreement’ are derived. The result will be supplemented through continuous discussions with facility operators and the government to be utilized for detailed system design.

Environmental justice is the principle, concept, and practice that all human beings should have equal and equitable rights to enjoy safe physical environment. Due to increasing pollutions caused by industrialization, economic development and man-made other activities, however, environmental justice is denied to various poor segments of populations across the world. In order to address the growing inequalities and inequities for safe environment to these affected communities, environmental justice movement has emerged and accelerated during the past few decades. This article presents an analysis of the concept and practices of environmental justice within a global context. The article also highlights the roles and responsibilities of the public, business and NGO sectors in promoting environmental justice

This article started with the purpose of discussing the need for research considering the historical context in sociolinguistic research. To this end, in this paper, the term ‘historical socilinguistics’ was first proposed, and the emphasis was placed on presenting the rationale. (1) Interest in language and society existed widely before the term sociolinguistics was coined. In particular, there are cases where the term 'sociology of linguistics' was used before the emergence of the term 'socilinguistics' mentioned in Lee Ik-seop (1994), mixtures are also found. (2) It was discussed that the interest in the relationship between language and society is to study the history of the language community, and that interest in the 'language community' has a long history in itself despite the diversity of concepts. (3) In this paper, the ‘history related to the linguistic phenomenon of a language community’ and ‘social factors as a linguistic environment’ are to be explored as ‘historical sociolinguistics’. (4) The need to study the historical and social factors of language change was discussed not only in terms of phonological, vocabulary, and grammatical changes, but also in the process of creation and settlement of translated academic terms.

2000년대 이후, 우리나라에서는 공립미술관이 대거 개관하면서 그 중요성을 새롭게 재인 식하는 시대를 맞이하였다. 이와 함께 공립작가미술관도 계속 증가해가며 그 입지를 더욱 강화해 가는 모습을 보여주고 있다. 요제프 슘페터는 새로운 것들의 끊임없는 결합과 적용을 통해 기존 의 것들을 혁신해나가는 ‘창조적 파괴’의 개념을 고안해냈다. 따라서 이 연구는 ‘이응노의집’에 초점을 맞춰 우리나라 공립작가미술관의 현황을 점검해보고, 창조적 파괴의 개념을 통해 이응노 의 예술세계를 기념하는 이응노의집의 미래경영 방안을 제언해 보고자 한다. 특히 이 연구는 근 대미술관이 부재한 한국의 미술관 현황을 고려하여 이응노의 예술세계를 핵으로 하는 근대미술 관으로 자리매김하는 이응노의집의 미래경영 전략과 방안을 구상해 보여주고자 한다.

In korea, 500MW standard coal fired power plants were designed and operated for the initial base load, so facility stability was prioritized from facility problem to treatment, but now we needed to research for minimizing greehouse gas emissions at the operation of coal fired power plants. research on various facilities and technologies was actively conducted to reduce environment pollutants was drastically reduced, but research and attempts on coping measures in the event of a reduction facility problem were in sufficient. this study considered investigated ways to minimized pollutants by quickly responding to logic development and application of the load runback concept in case of serious problems with environmental pollutant reduction facilities such as NOx reduction selective catalytic reduction facilities, SOx reduction wet flue gas desulpherisation facilities, and TSP(Total Suspended Particles) collection low temperature electric precipitator.