The small-waterplane-area-twin-hull(SWATH) ship has been recognized as a promising high performance ship because of her superior seakeeping characteristics and large deck area for various operations compared to the conventional monohull ship. significant advances in analytical technics for the prediction of the ship motions, wave loads and structural responses, structural fatigue and its prediction, and hull vibration for ship motions, wave loads and structural responses, structural fatigue and its prediction, and hull vibration for SWATH ship have been much developed during the last twenty years. Based on these developments in technology an integrated computational procedures for prediction wave loads and structural responses can be used to get a accurate results. But the major problem of SWATH ship's structural design is the accurate prediction of structural responses by the maximum critical loads likely to be experienced during the life of SWATH. To get a easier and safer computational procedures and the analytical approach for determining the accurate structural responses, a case study has been presented through the project experienced.

The objective of this study is to obtain the basic data for investigating the potentiality of continuous utilization (first cutting in the late fall and regrowth yield in next spring) of forage rape seeded in fall. Non-structural carbohydrates(NSC) in lea

지역별로 분포하고 있는 특성화된 온실의 장점을 살리고 구조적인 위험요소를 줄임으로서, 지역특성온실로 정착할 수 있도록 하기 위하여 지역별로 특성화된 온실의 구조실태를 조사하고 구조적 안전성을 검토하였으며 그 결과를 요약하면 다음과 같다. 1. 전남지방에 특성화된 온실의 보급이 많았으며, 광폭형하우스와 대형 단동 파이프하우스가 이 지역의 특성화된 온실로서 뚜렷한 경향을 나타내었다. 2. 경남 김해의 목재하우스, 전남 구례의 트러스형하우스, 강원 평창의 돔형 파이프하우스, 충북 옥천의 포도재배하우스 등이 특징적인 온실로 나타나고 있었다. 3. 광폭형하우스, 트러스형하우스, 돔형 파이프하우스 및 포도재배하우스는 15-30년 빈도의 풍하중과 설하중에 대하여 안전한 것으로 나타났으나, 대형 단동 파이프하우스는 약간의 보강이 필요하며, 목재하우스는 매우 불안정하여 사용을 중지하는 것이 좋을 것으로 판단되었다. 4. 대상온실의 기초는 모두 30년 빈도의 강풍에 대하여 충분한 인발저항력을 가지는 것으로 나타나 안전한 것으로 판단되었다.

재생기간중 저장 질소와 탄수화물의 이용을 구명하고자 수경재배 조건하에서 재배된 10주령의 알팔파(Medicago sativa L.)의 예취 후 재생 24일 동안 잔여기관내의 질소화합물 및 비구조성 탄수화물을 분석하였다. 재생초기 10일 동안 잔여기관내의 건물량에는 유의적인 변화가 없었으며, 비예취구와 비교할 때 예취는 뿌리성장(특히 주근)의 심각한 억제를 초래하였다. 잔여기관내의 질소함량은 재생초기 6일동안 유의적인 감소를 보였으며, 이 시기의 질소함량

본 연구는 생물생산시설의 구조설계 과정에서 초기단계의 고정하중을 합리적으로 추정하기 위한 식을 유도하여 구조설계 기준 설정에 기초자료를 제공하고, 생물생산분야 종사자가 간편하게 구조적 안전성을 진단할 수 있는 방법을 개발할 목적으로 수행하였으며 연구 결과를 요약하면 다음과 같다. 1. 국내의 온실설계자료를 수집하여 실제 하중을 산출, 분석해 본 결과 기존의 일본 시설원예기준 적용치와는 차이가 있었으며, 잠정적으로 국내 시설에의 적용을 위한 추정식을 유도하였다. 2. 지역별 설계하중을 적용하여 구조해석을 실시하고, 발생되는 응력의 크기에 따라서 풍하중 및 설하중 지배지역으로 안전설계 지역구분을 실시하였다.

본 연구는 생물생산시설의 안전구조설계기준 마련을 위한 기초자료를 제공하기 위하여, 우리나라의 60개 지역에 대한 기상자료를 사용하여 설계하중 산정에 필요한 재현기간별 설계풍속 및 설계 적설심을 구하고 등풍속선도 및 등적설심선도를 작성하였으며, 얻어진 결과를 요약하면 다음과 같다. 1. 년최고치 계열의 최대풍속 및 최대적설심 자료에 대한 Type-I 극치분포의 적정 확률분포형 검정을 위해 Chi-Square검정을 실시한 결과 대부분 지역에서 적합성이 인정되었다. 2. 적정 확률분포형으로 설정된 Type-I 극치분포에 의하여 재현기간별 표본 수에 따른 빈도계수를 구하고, 각 지역의 설계풍속 및 설계적설심을 구하였으며 결과는 Table 5와 Table 6, 그리고 Fig.3 및 Fig.4와 같다. 3. 최대풍속의 최빈풍향 분석결과 최대풍속의 약 46.4 %가 일정한 방향인 것으로 나타났으며, 지형이나 환경상의 문제가 없을 경우 최빈풍향을 고려해 주는 시설배치로 구조적 안전성을 향상시킬 수 있을 것으로 생각된다. 4. 우리나라의 풍속 및 적설심을 고려해 볼 때 울릉도 및 영동지방은 시설재배지역으로 매우 불리하며, 충남과 전북 서해안 지역은 적설에, 서남해안 지역은 바람에 강한 구조로 설계하는 것이 바람직하다는 것을 확인할 수 있었다.

In order to Characterizing the tea-culture of Korea, historical records for tea-culture of Korea, Japan and China were reviewed. The results were summarized as follows. 1. As for the type of tea through the history of Korea, it could be characterized as Cake-tea(餠茶) in Sam Kook dynasty, Iump-tea(硏膏茶) in Koryo dynasty and leaf tea(葉茶) in Chosun dynasty. Those were affected by Chinese and Japanese tea-culture. 2. Fashiono of tea-culture in Korea were unigue, imitative and reconstitutive. 3. It was concluded that the tea-culture in Korea might be established by the 'cult of tree' (樹木崇拜信仰) of Hwa Rang in Shilla dynasty.

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.

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.

Radioactive waste is typically disposed of using standard 200 and 320 L drums based on acceptance criteria. However, there have been no cases evaluating the disposal and suitability of 200 L steel drums for RI waste disposal. There has been a lack of prior assessments regarding the disposal and suitability of 200 L steel drums for the disposal of RI waste. Radioactive waste is transported to disposal facilities after disposal in containers, where the drums are loaded and temporarily stored. Subsequently, after repackaging the disposal drums, the repackaged drums are transported to disposal facilities by vehicle or ship for permanent disposal. Disposal containers can be susceptible to damage due to impacts during transportation, handling, and loading, leading to potential damage to the radiation primer coating during loading. Additionally, disposal containers may be subject to damage from electrochemical corrosion, necessitating the enhancement of corrosion resistance. Metal composite coatings can be employed to enhance both abrasion resistance and corrosion resistance. The application of metal composite coatings to disposal containers can improve the durability and radiation shielding performance of radioactive waste disposal containers. The thickness of radioactive waste disposal containers is determined through radioactive shielding analysis during the design process. The designed disposal containers undergo structural analysis, considering loading conditions based on the disposal environment. This paper focuses on evaluating the structural improvements achieved through the implementation of metal composite coatings with the goal of enhancing corrosion and abrasion resistance.