Because most spent nuclear fuel storage casks have been designed for low burnup fuel, a safety-significant high burnup dry storage cask must be developed for nuclear facilities in Korea to store the increasing high burnup and damaged fuels. More than 20% of fuels generated by PWRs comprise high burnup fuels. This study conducted a structural safety evaluation of the preliminary designs for a high burnup storage cask with 21 spent nuclear fuels and evaluated feasible loading conditions under normal, off-normal, and accident conditions. Two types of metal and concrete storage casks were used in the evaluation. Structural integrity was assessed by comparing load combinations and stress intensity limits under each condition. Evaluation results showed that the storage cask had secured structural integrity as it satisfied the stress intensity limit under normal, off-normal, and accident conditions. These results can be used as baseline data for the detailed design of high burnup storage casks.
선박 건조 과정에서 블록이나 장비를 지지하는 A형 캐리어 구조는 하중 변경과 시간이 지남에 따라 점차 변형이 증가하며, 이 에 따라 블록과 접촉하는 면적이 감소하고 분산된 하중에서 집중된 하중으로 패턴이 변화한다. 이러한 현상은 실제 사용 하중을 오판할 가능성이 있다. 특히 A형 캐리어는 영세한 제조 업체에서 자주 사용하고 있으며, 별도의 엔지니어링 기능이 없는 상황이 대부분이라서 손 쉽게 캐리어의 안전사용하중을 계산하는 방법의 개발이 필요하다. 본 연구는 A형 캐리어가 장기적으로 안전하게 사용할 수 있는 하중을 신속하게 평가하는 방법을 제안함으로써, 하중 분포의 변화에 따른 소성 변형과 그로 인한 안전 문제를 예측하고 대응할 수 있다. 제안된 방법은 캐리어의 중앙 집중하중과 전체 분포하중 조건에 대해서 유한요소해석(빔, 쉘 모델링)을 통한 결과를 기반으로 빔-이론을 수정하 여 제안되었다. 빔 모델링에서 집중하중 조건은 보정계수 0.73, 분포하중에서는 0.69를 이론값에 곱해서 안전사용하중이 가능하다. 쉘 모 델링의 경우, 집중하중은 0.75와 분포하중은 0.69를 사용할 수 있다. 본 연구는 선박 건조 작업 현장의 안전을 개선하고, 실제 작업 환경에 서의 안전 사용 하중 판단에 신속하고 효과적인 결정을 내릴 수 있는 기초 자료로 활용될 수 있다.
본 논문에서는 조선 후기의 대표적인 전통목구조인 수원 화령전 운한각의 구조성능을 평가하였다. 운한각의 가구구성 방식에 맞추 어 3차원 구조해석 소프트웨어인 midas Gen으로 해석모델을 정교하게 구축하였다. 정적해석으로 주요 구조부재의 안전성과 사용성 을 평가하였고, 고유치해석으로 동적거동특성을 평가하였다. 대부분의 부재가 안전성 및 사용성 기준을 여유 있게 만족하고 있으나, 외목도리에서 휨응력비가 기준을 20.7% 초과하고 있어 이 부재에 대해서는 장기적인 모니터링이 필요하다고 사료된다. 운한각의 고 유주기는 1.079초로 비슷한 규모의 전통목구조보다 약간 긴 편이며, 특히 후면 화방벽의 영향으로 2차모드에서 비틀림이 발생한 것으 로 분석된다.
The cultural heritage of fortresses is often exposed to external elements, leading to significant damage from stone weathering and natural disasters. However, due to the nature of cultural heritage, dismantling and restoration are often impractical. Therefore, the stability of fortress cultural heritage was evaluated through non-destructive testing. The durability of masonry cultural heritages is greatly influenced by the physical characteristics of the back-fille material. Dynamic characteristics were assessed, and endoscopy was used to inspect internal fillings. Additionally, a finite element analysis model was developed considering the surrounding ground through elastic wave exploration. The analysis showed that the loss of internal fillings in the target cultural heritage site could lead to further deformation in the future, emphasizing the need for careful observation.
In this study, the SBC system, a new mechanical joint method, was developed to improve the constructability of precast concrete (PC) beam-column connections. The reliability of the finite element analysis model was verified through the comparison of experimental results and FEM analysis results. Recently, the intermediate moment frame, a seismic force resistance system, has served as a ramen structure that resists seismic force through beams and columns and has few load-bearing walls, so it is increasingly being applied to PC warehouses and PC factories with high loads and long spans. However, looking at the existing PC beam-column anchorage details, the wire, strand, and lower main bar are overlapped with the anchorage rebar at the end, so they do not satisfy the joint and anchorage requirements for reinforcing bars (KDS 41 17 00 9.3). Therefore, a mechanical joint method (SBC) was developed to meet the relevant standards and improve constructability. Tensile and bending experiments were conducted to examine structural performance, and a finite element analysis model was created. The load-displacement curve and failure pattern confirmed that both the experimental and analysis results were similar, and it was verified that a reliable finite element analysis model was built. In addition, bending tests showed that the larger the thickness of the bolt joint surface of the SBC, the better its structural performance. It was also determined that the system could improve energy dissipation ability and ductility through buckling and yielding occurring in the SBC.
In this study, the shape evaluation and design of the spare tire carrier for SUV (sports utility vehicle) were addressed through structural analysis. Spare Tire Carrier analysis was conducted to evaluate rigidity, and strength and improvement measures for appropriate shapes were found and reflected in the design. Through structural analysis of the spare tire carrier, this study was conducted to derive an optimal design plan as the stiffness and strength needed to be increased for stable installation of the spare tire carrier. Compared to the existing model, the bar, which was curved, was changed to a straight line to shorten the length, thereby increasing rigidity. In addition, because the moment was concentrated in the structure of the rear hanger mounting bracket, the side part of the bracket was extended, but the cross member stiffness was relatively weak, so it did not have a significant effect.
In this study, the shape evaluation and design of clamp mount for SUVs (sports utility vehicles) was dealt with through structural analysis. The clamp mount analysis was performed to evaluate stiffness, strength and improvement plans for appropriate shape were found and reflected in the design. In addition, strength analysis and was performed in parallel to solve the problem of rib design around the edge part of the clamp mount and the thickness effect results were reflected in the design. As a result of analysis through various design changes, it was possible to present an appropriate reinforcement design shape. In addition, when the thickness of the fuel tank was changed from 3.2mm to 4.0mm, the stiffness of the fuel tank decreased by approximately 30%, and reinforcement was required.
구조물 보수 부위의 손상, 재 박리 등의 2차 피해가 이어지며, 보수 부위의 새로운 거동 평가 기법 에 대한 연구의 필요성이 대두되고 있다. 현재 구조물 보수 부위의 거동을 알기 위해서 주로 인력 중 심의 구조물 외관 검사를 진행하고 있으나, 단편적인 검사 결과를 얻게 되어 지속적이고 세밀한 점검 이 어려운 실정이다. 따라서, 본 연구에서는 탄소나노튜브 기반 폴리머 콘크리트를 활용해 압축과 같 은 외부 응력에 대한 탄소나노튜브 함량별 전기적 변화를 분석하였으며, 균열이 발생한 콘크리트 구조 물을 보수 후 응력을 가해 거동에 따른 전기적 변화를 평가하였다. 압축 시험 결과, 응력에 따른 탄소 나노튜브 기반 폴리머 콘크리트의 전기 저항이 감소하며, 탄소나노튜브 함량이 낮을수록 응력에 대한 저항 감소 폭이 넓게 나타나며 민감도가 증가하였다. 균열 보수 시험 결과, 보수 부위에 응력이 가해 졌을 때 전기 저항이 감소해 앞서 진행된 실험 결과와 동일한 경향을 보였으며, 또한 응력이 가해지지 않을 때 초기 저항으로 회복하는 경향을 보여 구조물 보수 부위 거동에 대한 평가가 가능한 것으로 검 증되었다. 이를 통해, 탄소나노튜브 기반 폴리머 콘크리트는 구조물에 적용이 가능하며, 구조물 보수 후에도 가해지는 응력에 대한 지속적인 감지가 가능해 보수 부위 거동 평가가 가능할 것으로 판단된다.
해상풍력발전 시장의 성장과 함께 해상풍력발전기 설치 선 시장에 대한 기대감이 커지고 있다. 해상풍력발전 시장 내 2030년까 지 약 100척의 설치 선이 필요할 것으로 전망되고 있다. 척당 가격이 3,000∼4,000억 원이라서 일반 운반선보다 고부가가치 시장이다. 특 히, 풍력발전기 용량이 11MW 이상의 대형 설치 선의 수요가 커지고 있다. 중국을 중심으로 아시아 해상풍력발전기 시장의 급성장으로 이 지역에서 운용 가능한 설치 선에 대한 발주에 대한 협의가 많다. 아시아권역 대부분의 해저 지질은 지지 반력이 작은 점토층으로 구성되 어 있다. 이러한 특성에 의해서 설치 선이 작업을 위해 수면 밖으로 오르고 내림 시 스퍼드캔(Spudcan)과 레그(Leg)의 관입 깊이가 크게 발 생한다. 연구에서는 최소 3m에서 최대 21m까지 관입 변수를 이용하여 관입 깊이에 따른 고유 진동 주기, 레그의 구조 안전성 평가 그리고 전복 안전성 지수를 평가하였다. 관입 깊이가 증가하면 고유 진동 주기가 짧아지고, 레그의 모멘트 길이가 짧아져서 구조 강도의 여유 치 가 증가한다. 모든 입사각에서 전복 모멘트에 대해 안전하며, 최댓값은 270도에서 발생한다. 본 연구를 통하여 검토된 조건들은 연약 지반 에서 설치 선의 운용 절차서를 작성 시 관입 깊이에 따라서 레그를 어떻게 운용해야 하는지 판단할 수 있는 중요한 자료로 활용할 수 있 다. 결론적으로 관입 깊이에 따른 레그 구조 안전성을 정확히 파악하는 것은 설치 선의 안전과 직결된 문제이다.
본 논문은 조선시대의 대표적인 중층 목구조인 공주 마곡사 대웅보전에 대하여 수직하중에 대한 구조성능을 평가하였다. 구조해석 소프트웨어인 midas Gen으로 실물과 근접하게 해석모델을 3차원으로 구축하였다. 정적해석으로 수직하중에 대한 주요 수직 및 수평 부재의 안전성과 사용성을 평가하였다. 모든 부재가 안전성과 사용성 기준을 만족하였으나, 하층 대량은 전이보 역할로 구조적 취약 점이 나타나 개선의 필요가 있다. 동적거동특성 평가를 위한 고유치해석시 주요 접합부의 상대회전강성은 5%로 가정하였다. 고유주 기는 1.105초로 비슷한 규모의 한옥 범주에 속하고 있으며, 1차 모드는 건물 전후방향의 병진운동으로 나타났다.
The aim of this study is to ensure the structural integrity of a canister to be used in a dry storage system currently being developed in Korea. Based on burnup and cooling periods, the canister is designed with 24 bundles of spent nuclear fuel stored inside it. It is a cylindrical structure with a height of 4,890 mm, an internal diameter of 1,708 mm, and an inner length of 4,590 mm. The canister lid is fixed with multiple seals and welds to maintain its confinement boundary to prevent the leakage of radioactive waste. The canister is evaluated under different loads that may be generated under normal, off-normal, and accident conditions, and combinations of these loads are compared against the allowable stress thresholds to assess its structural integrity in accordance with NUREG-2215. The evaluation result shows that the stress intensities applied on the canister under normal, off-normal, and accident conditions are below the allowable stress thresholds, thus confirming its structural integrity.
A transfer cask serves as the container for transporting and handling canisters loaded with spent nuclear fuels from light water reactors. This study focuses on a cylindrical transfer cask, standing at 5,300 mm with an external diameter of 2,170 mm, featuring impact limiters on the top and bottom sides. The base of the cask body has an openable/closable lid for loading canisters with storage modules. The transfer cask houses a canister containing spent nuclear fuels from lightweight reactors, serving as the confinement boundary while the cask itself lacks the confinement structure. The objective of this study was to conduct a structural analysis evaluation of the transfer cask, currently under development in Korea, ensuring its safety. This evaluation encompasses analyses of loads under normal, off-normal, and accident conditions, adhering to NUREG-2215. Structural integrity was assessed by comparing combined results for each load against stress limits. The results confirm that the transfer cask meets stress limits across normal, off-normal, and accident conditions, establishing its structural safety.
The design of buried underground flexible pipes proposed in domestic standards does not properly reflect changes in ground characteristics. Overseas standards suggest that pipe deflection must be considered while designing them. Therefore, in this study, the structural behavior of underground polyvinyl chloride pipes was investigated through experiments and the finite element analysis. In addition, when the pipe deflection occurred at 3% and 5%, the hydraulic characteristics of the polyvinyl chloride pipe showed a slight difference compared to the round pipe.
Herein, the existing structural design criteria for highway bridge columns with hollow bars were analyzed. Expanding upon previous research focused on the performance analysis of the columns under compressive loads, load– displacement curves were evaluated and crack analysis was performed under cyclic transverse loads. A three-dimensional nonlinear finite-element structural analysis compared the structural performance of existing steel bars, same-reinforced hollow bars, and reduced hollow bars in detail. Results indicated that with regard to elastic or initial crack behavior, the existing steel bars can be replaced by the other bars. Future research should delve into inelastic behavior and strategies to ensure seismic performance.
The operation time of a disposal repository is generally more than one hundred years except for the institutional control phase. The structural integrity of a repository can be regarded as one of the most important research issues from the perspective of a long-term performance assessment, which is closely related to the public acceptance with regard to the nuclear safety. The objective of this study is to suggest the methodology for quantitative evaluation of structural integrity in a nuclear waste repository based on the adaptive artificial intelligence (AI), fractal theory, and acoustic emission (AE) monitoring. Here, adaptive AI means that the advanced AI model trained additionally based on the expert’s decision, engineering & field scale tests, numerical studies etc. in addition to the lab. test. In the process of a methodology development, AE source location, wave attenuation, the maximum AE energy and crack type classification were subsequently studied from the various lab. tests and Mazars damage model. The developed methodology for structural integrity was also applied to engineering scale concrete block (1.3 m × 1.3 m × 1.3 m) by artificial crack generation using a plate jacking method (up to 30 MPa) in KURT (KAERI Underground Research Tunnel). The concrete recipe used in engineering scale test was same as that of Gyeongju low & intermediate level waste repository. From this study, the reliability for AE crack source location, crack type classification, and damage assessment increased and all the processes for the technology development were verified from the Korea Testing Laboratory (KTL) in 2022.