In this research, a detailed analysis of the decay heat contributions of both actinides and non-actinides (fission fragments) from spent nuclear fuel (SNF) was made after 50 GWd·tHM−1 burnup of fresh uranium fuel with 4.5% enrichment lasted for 1,350 days. The calculations were made for a long storage period of 300 years divided into four sections 1, 10, 100, and 300 years so that we could study the decay heat and physical disposal ratios of radioactive waste in medium- and long-term storage periods. Fresh fuel burnup calculations were made using the code MCNP, while isotopic content and then decay heat were calculated using the built-in stiff equation solver in the MATLAB code. It is noted that only around 12 isotopes contribute more than 90% of the decay heat at all times. It is also noted that the contribution of actinides persists and is the dominant ether despite decreasing decay heat, while the effect of fission products decreases at a very rapid rate after about 40 years of storage.

In order to ensure the long-term safety of a deep geological repository, the performance assessment of the Engineered Barrier System (EBS) considering a thermal process should be performed. The maximum temperature at the side wall of a disposal canister for the technical design requirement should not exceed 100°C. In this study, the thermal modelling was conducted to analyze the effects of the thermal process from a disposal canister to the surrounding near-field host rock using the PFLOTRAN code. The mesh was generated using the LaGriT code and the material properties were assigned by applying the FracMan code. Initial conditions were set as the average geothermal gradient (25.7°C/km) and an average surface temperature (14.7°C) in Korea. The highest temperature was observed at the middle of the canister side wall. The temperature of the buffer was lower than that of the canister, and the temperature increase of the deposition tunnel and the host rock was insignificant due to the lower effect of the heat source. The result of the thermal evolution of the EBS represented the highest thermal effects in the vicinity of the canister. In addition, the thermal effects were largely decreased after 10 years of the entire simulation period. It demonstrated that the model took 3 years to heat up the buffer around the canister. The temperature at the canister side wall increased until 3 years and then decreased after that time. This is because that the radioactive decay heat from the heat source was emitted enough to raise the overall temperature of the EBS by 3 years. However, the decay heat rate of the canister decreased exponentially with the disposal time and then its decay heat was not emitted enough after 3 years. In conclusion, the peak temperature results of the EBS were lower than 70°C to meet the technical design requirement.

A methodology is under development to reconstruct and predict the long-term evolution of the natural barrier comprising the site of radioactive waste disposal. The natural barrier must protect the human zone from radionuclides for a long time. So for this, we need to be able to restore the evolution of the bedrock constituting the natural barrier from the past to the present and to predict from the present to the future. A methodology is being studied using surface outcrop, tunnel face of KURT (KAERI Underground Research Tunnel), and drill core at KAERI (Korea Atomic Energy Research Institute). Among them, drill core is an essential material for identifying deep geological properties, which could not be confirmed near the surface when considering the geological condition of the repository in the deep part. In this study, we selected several qualitative and quantitative analyses to construct a deep lithological model from the disposal perspective. These were applied to drill core samples around the KURT. There are the dikes presumed the Cretaceous were intruded by Jurassic granitoids in the study area. Analyzing trace elements of each rock type in the study area classified through geochemical characteristics and microstructure in previous studies made it possible to obtain qualitative information on the petrogenetic process. In addition, synthesizing the quantitative numerical age allows for grasping the evolution of bedrock, including intrusion and cutting relationships. LAICPMS was used for determining the age of zircons in plutonic rocks. The highly reliable 40Ar-39Ar method was selected for volcanic rocks because it can correct the loss of Ar gas and obtain the values of two types of Ar isotopes in a single sample. As a result, it was possible to infer the formation environment of rocks through anomalies in specific trace element content. And according to the numerical ages, it was possible to support the known separated rock type found in previous studies or to present a quantitative precedence relation for unclassified rocks. These methods could be applied to reconstruct the long-term evolution of bedrock within natural barriers.

해양사고 예방을 위해서는 사고의 원인과 결과에 대한 분석 및 진단뿐만 아니라, 사고의 발생 패턴과 변화 추이를 예측함으로 써 정량적 위험도를 제시할 필요성이 있다. 선박교통과 관련된 해양사고 예측은 선박의 충돌위험도 분석 및 항해 경로 탐색 등 선박교통 의 흐름에 관한 연구가 주로 수행되었으며, 해양사고의 발생 패턴에 대한 분석은 전통적인 통계 분석에 따라 제시되었다. 본 연구에서는 해양사고 통계 자료 중 선박교통관련 사고의 월별, 시간대별 발생 현황 데이터를 활용하여 해양사고 발생 예측 모델을 제시하고자 한다. 국내 해양사고 발생 현황 중 월별, 시간대별 데이터 집계가 가능한 1998년부터 2021년까지의 통계자료 중 선박교통 관련 데이터를 분류하 여 정형 시계열 데이터로 변환하였으며, 대표적인 인공지능 모델인 순환 신경망 기반 장단기 기억 신경망을 통하여 예측 모델을 구축하 였다. 검증데이터를 통하여 모델의 성능을 검증한 결과 RMSE는 초기 신경망 모델에서 월별 52.5471, 시간대별 126.5893으로 나타났으며, 관측값으로 신경망 모델을 업데이트한 결과 RMSE는 월별 31.3680, 시간대별 36.3967로 개선되었다. 본 연구에서 제안한 신경망 모델을 기 반으로 다양한 해양사고의 특징 데이터를 학습하여 해양사고 발생 패턴을 예측할 수 있을 것이다. 향후 해양사고 발생 위험의 정량적 제 시와 지역기반의 위험지도 개발 등에 관한 추가 연구가 필요하다.

본 연구에서는 칠발도, 거문도, 동해에서 20년 이상 관측된 파랑자료를 16 방위별 극치확률분석을 통해 재현빈도별 심해설 계파를 산정하였고, 이 값을 방향을 고려하지 않은 전방향파의 심해설계파와 비교하였다. Weibull 분포함수를 확률분포함수로 사용하였 으며, 최소자승법을 사용해서 매개변수를 결정하였다. 추정된 분포함수는 Kolmogorov-Smirnov 방법을 사용하여 적합도를 검증하였다. 그 결과 방향별로 구한 심해설계파가 전방향파의 심해설계파보다 모든 방향에서 상대적으로 작은 것으로 나타났다. 파향별로 구한 50년 빈도 설계파고는 칠발도, 거문도, 동해에서 각각 7.46 m(NNE), 12.05 m(S), 9.69 m(SSW)가 최대값이지만, 전방향파로 구한 설계파고는 각각 7.91 m, 13.82 m, 10.38 m이었다. 이는 현재 해양 및 연안 구조물 설계에 사용하고 있는 16 방위별 심해설계파고가 과소산정되었을 가능 성이 있음을 보여준다.

During the normal operation boron concentrates and spent resins are generated. The boron concentrates are treated by concentrated waste drying system (CWDS) and results in fine powder form. The solidification or application of high integrity container (HIC) is required for the disposal of the dried boron concentrates. The spent resin is stored in storage tank after the water treatment. The spent resin also requires solidification or application of HIC to satisfy the waste acceptance criteria (WAC) in Korea. The solidification process requires periodic validation. The repeated validation and complicated process hesitates the practical application. The application of HIC offers various advantages, including flexible free standing water requirement, higher waste loading compared to solidification, and simple process. The polymer concrete (PC), which is a primary component for PC-HIC exhibits good material stability. The expected transportation mechanism of nuclide in the PC-HIC are 1) diffusion by concentration, 2) permeation by pressure, and 3) capillary suction when considering the disposal condition. Since the PC-HIC effectively prevents the intrusion of neighboring water and volume of free standing water is lower than 1%, it seems that diffusion by concentration is the primary transportation mechanism. In this study, the property of PC is investigated based on Cl ion diffusion test to evaluate the material reliability. The results indicate that PC exhibits superior stability compared to ordinary portland cement. In addition, the reliable life time of PC is estimated base on the element transportation phenomena.

Since it takes hundreds of thousands of years for the radiotoxicity of spent nuclear fuel to decrease to natural levels, interactions between each repository barrier, climate change, and geological evolutions are inevitable. These processes should be defined as the long-term evolution FEPs and considered in the performance assessment to ensure the long-term safety of the disposal system. The literature survey on geological characteristics and history of the Korean peninsula was conducted, and the list of A-KRS-FEPs which are directly or indirectly related to long-term evolutions was identified in this study. The ice age and geological change are the capital phenomena considered in the exceedingly long-term evolution before/after climate change. The historical data on ice sheets and permafrost were analyzed to investigate the effects of the ice ages on the Korean peninsula. The sealevel changes were investigated based on the research on the coastal terrace to identify the impact on uplift and shoreline change accompanying the ice age. Also, the survey on the geological history data was conducted from the perspective of tectonic activity, metamorphism, igneous activity, and seismic activities to consider the geodynamic evolution of the Korean peninsula. As results, it was suggested that 14 FEPs were directly related to climate change, 18 FEPs were directly related to geological evolution, and 47 FEPs were indirectly relevant to long-term geodynamics. The consent-based FEPs and scenarios for the long-term evolution will be developed shortly, including most of the critical long-term evolution phenomena defined in this study and which are highly probable in domestic disposal conditions. The evaluation and verification of the APro system for long-term safety will accomplish using these FEPs and scenarios.

Deep geologic repositories (DGR) are designed to store spent nuclear fuel and to isolate it from the biosphere for an extended period of time as long as millions of years. The long-term performance of the DGR replies on the performance of the natural geologic barriers after the end of the lifetime for the engineered barrier systems. Typically, multiple analytical and numerical models are used to analyze and ensure the safety of the repositories along both engineered and natural barrier systems. Despite the immense advancement in computing power and modeling techniques over the last few decades, a series of models and their linkage often require many simplifying assumptions in this safety assessment. The degree of the reliability and confidence of the safety analysis is thus highly dependent on the validity of those tools used. Considering the significance of the DGR performance and public attention, the highest level of quality control is necessary for the models employed in the assessment. The performance of the ultimate long-term geologic barrier is determined by the expected travel time of the radioactive species of interest, the level of their dilution or radioactivity at compliance areas, and the uncertainty associated with them. As the species of interest can be carried away from the repository location by groundwater flow, the travel time is determined by groundwater velocity along the flow path from source to biosphere while the dilution is a function of the decay and production rates as well as the diffusion and dispersion. Due to the time scale and the complexity of the physicochemical processes and geologic media involved, the models used for safety evaluation will need to become more and more comprehensive, robust, and efficient which is difficult to achieve in principle. They will also need to be transparent and flexible to satisfy the regulatory quality control requirements. This study thus attempts to develop an accessible, transparent, and extensible integrated hydrologic models (IHM) which can be widely accepted by the regulators as well as scientific community and thus suitable for current and future safety assessment of the DGR systems. The IHM can be considered as a tool and a framework at the same time when it is designed to easily accommodate additional processes and requirements for the future as it is necessary. The IHM is capable of handling the atmospheric, land surface, and subsurface processes for simultaneously analyzing the regional groundwater driving force and deep subsurface flow, and repository scale safety features, providing an ultimate basis for seamless safety assessment in the DGR program. The applicability of the IHM to the DGR safety assessment is demonstrated using simple illustrative examples.

초고층 건물에서 수평변위 제어와 수직부재에서 발생하는 부등축소에 대한 검토가 필수적이다. 이러한 부등축소는 비구조요소의 사용성과 구조요소의 안전성에 대해 문제를 야기할 수 있다. 따라서 이 연구에서는 120층 규모의 철근콘크리트 주거용 초고층 건물에 대해 시공단계해석을 수행하여 각 수직부재의 부등축소량을 비교하고 콘크리트의 장기거동의 영향을 분석하였다. 이를 위해 영향요 인에 따라 축소량을 탄성축소량, 크리프축소량, 건조수축축소량으로 구분하여 검토하였으며 최대 절대축소량에 대한 지배적 요인을 분석하였다. 또한, 입주완료 후 30년에서 발생한 부등축소량에 대해 사용성 검토를 진행하였으며, 구조요소에 대해 설계단계와 시공 단계의 부재력을 비교하여 분석하였다.

PURPOSES : In this study, the results of an intensive field survey of a composite pavement applied to an expressway in Korea are analyzed. The results are intended to be used as basic data for evaluating the composite pavement and for preparing quality control measures through a review and analysis of the change in the state of the tensile bonding strength of the composite pavement. METHODS : To evaluate, repeated field coring and indoor tensile bonding strength evaluations are conducted for five years, and the commonality evaluation of pavement using pavement condition investigation equipment is conducted annually. RESULTS : The results of this study show that the degree of reflective crack generation varies depending on the type of concrete pavement and type of asphalt mixture applied to the intermediate layer, and that the CRCP composite pavement exhibits better initial commonality than the JCP composite pavement. In addition, it is confirmed that the composite cross-section pavement section with MASTIC applied as an intermediate layer shows excellent adhesion performance between the lower concrete layers from the beginning of construction in all sections, as well as satisfied the quality control standards for good pavement and tensile adhesion even after approximately five years of public use. CONCLUSIONS : Based on a follow-up survey of the composite pavement testing sections, it is confirmed that the section constructed with the MASTIC intermediate layer and CRCP satisfies the quality control standards for good pavement conditions and tensile adhesion even after approximately five years of public use.

Currently, the interim storage pools of spent fuels in South Korea are expected to become saturated from 2024. It is required to prepare an operation plan of a domestic dry storage facility during a long-term period, with the researches on safety evaluation methods. This study modified the FRAPCON code to predict the spent fuel integrity evaluation such as the axial cladding temperature, the hoop stress and hydrogen distribution in dry storage. The cladding temperature in dry storage was calculated using the COBRA-SFS code with the burnup information which was calculated using the FRAPCON code. The hoop stress was calculated using the ideal gas equation with spent fuel information such as rod internal pressure. Numerical analysis method was used to calculate the degree of hydrogen diffusion according to the hydrogen concentration and temperature distribution during a dry storage period. Before 50 years of dry storage, the cladding temperature and hoop stress decreased rapidly. However, after 50 years, they decreased gradually and the cladding temperature was below 400 K. The initial temperature distribution and hydrogen concentration showed a parabolic line, but hydrogen was transferred by the hydrogen concentration and temperature gradient over time.

본 연구는 전국자연환경조사 어류 데이터를 이용하여 국내 담수 생태계에 도입된 배스의 분포 현황을 파악하고 공간분석을 통해 핫스팟 지역을 분석하였다. 위해성 평가를 통해 배스의 잠재적 침습성을 평가하여 수생태계 생물 다양성 교란에 대한 영향을 재고하였다. 분포 분석 결과, 제주도 지역을 포함하여 한강권역과 낙동강권역, 금강권역, 영산강·섬진강권역 전체에서 분포하는 것으로 분석되었다. 낙동강권역에서 가장 높은 출현율을 나타내었으며, 제주도 지역을 제외한 영산강·섬진강권역에서 비교적 낮은 출현율을 나타내는 것으로 분석되었다. 배스의 공간적 군집 밀도가 높은 지역으로는 낙동강권역의 낙동강수계가 선정되었으며, 반대로 낮은 지역으로는 한강권역과 금강권역의 인접한 지역으로 분석되었다. 국내 대부분의 담수하천에 서식하는 것으로 나타난 배스의 위해성 평가를 실시한 결과, 31점의 높은 침습성을 보이는 것으로 분석되었다. 본 연구를 통해 우리나라 담수 생태계에 정착한 것으로 파악되는 생태계교란종인 배스로부터 실질적인 관리 우선지역을 도출하여 담수 생태계 다양성 보전을 위한 과학적 기초자료를 마련할 수 있을 것으로 전망한다.

목적 : 본 연구의 목적은 장기요양서비스에서 작업치료 인력의 공급현황과 공급추계를 분석하고, 수요추계와의 비교를 통해 향후 장기요양 시장에서의 작업치료사 인력 수급 정책의 방향에 대해 논의하는 것이다. 연구방법 : 장기요양시장에서의 작업치료사 인력 공급현황과 공급추계를 위한 연구자료는 보건복지부의 각 연도별 보건복지통계연보와 국민건강보험공단의 작업치료사 활동현황에 대한 내부자료(2008년~2018 년)를 활용하였다. 작업치료사 인력 공급추계는 인력변화 추이에 대한 시계열 자료를 이용하여 이러한 추이가 앞으로 계속 유지된다는 가정 하에 장래 인력을 추계하는 총수방법을 활용하였고, 기술통계분석을 통해 합계 및 평균치(전년대비 증가율, 3년 평균 증가율 등)등을 구하였다. 결과 : 장기요양기관에서 활동 중인 작업치료사는 2008년 41명에서 2018년 758명으로 지속적으로 증가 하였고, 이를 연평균 증가율로 환산하면 37.8%로 나타났다. 작업치료사 인력 증가율(전년대비 증가율 또는 3년 연평균 증가율)이 계속 유지된다고 가정하면, 2020년에서 2030년에 걸쳐 인력에 대한 수요에 비해 공급이 과잉되는 것으로 나타났다. 결론 : 질 높은 서비스를 제공하기 위해 무엇보다 장기요양서비스 내 작업치료 인력의 수급 불균형의 문제를 해결하고 적정 인력 공급과 관리를 위한 정책적 노력이 필요하다. 정부의 장기요양서비스에서의 작업 치료사 인력 수급 정책의 방향이 지금까지 인력의 양적 공급에 주목한 것이라면 앞으로는 작업치료사가 장기요양시장에 진입하여 잘 정착할 수 있도록 저임금 등의 노동환경을 개선하는 등의 인력 질적 관리로 전개될 필요가 있어 보인다.

Strong naval power is needed to protect the sea, the lifeline of the national economy and people's lives. The navy has been operating with the increase of forces and the selection of officers to achieve its mission, and long-term service officers are selected every year. In this study, problems were identified through the analysis of relative influence of the long-term service selection system for naval officers by evaluation factors. As a result of relative influence on the selection data for long-term service of 203 officers over the past 3 years(2018∼2020) showed education results(25.05%) > english ability(23.33%) > work evaluation(11.23%) > prize(10.91%). In order to equal the relative influence and the rate of allocation by evaluation factors, higher the score of work evaluation, command recommendation, and physical strength, lower the score of education results, english ability, and prize were required. Sensitivity analysis was conducted after suggesting the alternatives that adjusted the scoring by ±2∼5, ±2∼10 points. As a result of calculating the relative influence on the alternatives, rankings of the score and the relative influence gradually became similar.

2020년 7월에 도시계획시설(공원) 실효제가 시행됨에 따라, 본 논문에서는 서울시 근린공원 중 시민의 이용과 사유지가 많은 미집행 근린공원 35개소를 대상으로 공원이 실효되기 전 보상 및 관리방안을 마련하기 위한 연구를 진행하였다. 선행연구 분석, 현장조사, GIS분석 및 전문가의 자문 등을 통해 공원 특성에 따른 장·단기적 대응지 분류기준 및 공원보상 우선순위 기준 마 련하였다. 연구내용은 실효시기를 기준으로 장·단기적 대응지를 구분하여 단기적 대응지는 ‘접근성, 이용성, 관리성’에 따라 3가지의 순위로 구분하였으며, 장기적 대응지는 국공유지, 중 복규제지, 접근성 취약지, 공원기능 상실지로 구분하였다. 연구결과 대부분의 근린공원은 필지 별로 특성이 상이하여 공원 내 장·단기적 대응지가 혼재하여 분포하고 있는 것으로 확인되었 으며, 특히 까치산, 염창, 영축산, 고덕 등은 단기적 대응지의 보상필요면적의 20% 이상이므로 집행이 시급한 것으로 나타났다. 또한 장기적 대응지 중 국공유지의 비율이 80% 이상인 낙산, 청량, 배봉산, 계남, 노량진, 불광, 와룡과 중복규제지의 비율이 공원 내 50% 이상인 세곡, 광 평, 고덕의 경우 해당 항목의 분포 비율이 높으므로 각 규제에 따라 공원별 통합 관리가 가능할 것으로 사료된다.