본 연구는 강풍에 취약한 설비로 선정된 154kV 직선형 송전철탑을 대상으로 극한 풍하중에 대한 구조 성능을 검토하였다. 선행연 구에 따르면 송전철탑은 정면풍보다 45° 풍향에서 더 취약한 거동을 보이며, 이를 고려하여 ABAQUS를 이용한 Pushover 해석을 수 행하였다. 극한 풍속 조건에서의 취약 부재와 거동 특성을 분석한 후, 길이 차원에서 1/2 상사율을 적용한 부분축소모형을 제작하였 으며, 지압이음 조건과 마찰이음 조건으로 구분하였다. 또한 두 대의 가력기를 이용해 전체모델에서 산정된 수평력과 휨모멘트를 상 사법칙에 따라 재현하였다. 실험 결과, 볼트 체결력을 향상시킨 경우 항복변위는 약 30% 감소했으나 항복하중에는 큰 차이가 없었다. 특히 마찰이음 조건에서는 해석과 실험의 항복하중 및 항복변위가 모두 5% 이내의 오차를 보여 Pushover 해석의 신뢰성이 검증되었다. 향후 연구에서는 주요 부재의 보강 방안을 수립하고, 보강된 부분축소모형 실험을 통해 내풍 및 내진 성능 향상을 검증할 예정이다.
프리캐스트 코핑의 중공부 주철근 단절로 인한 단점을 보완하고, 거치대 삽입 없이 주철근을 거치대로 활용할 수 있 도록 철근-콘크리트 접촉부의 응력집중을 완화할 수 있는 하중분산세트의 성능을 검토하였다. 유한요소해석 및 축소모형실험을 통해 검토한 결과 하중분산세트는 철근-콘크리트 접촉부의 응력집중을 효과적으로 완화시켜 거치 시 콘크리트 파손을 방지할 수 있을 것으로 판단된다.
Many studies are conducted in several fields for fragility analysis of structures or elements which is a probabilistic seismic safety analysis in consideration with uncertainty of seismic loading. It is hard to directly conduct fragility analysis for an infrastructure with social importance due to its size. Therefore, a fragility analysis for an infrastructure mainly conducted in element level or conducted with scaled model built in accordance with similarity law. In this article, fragility analysis for prototype and scaled model of reinforced concrete column was conducted with numerical models which had been updated by the results of shaking table test and pseudo dynamic test. As a result, response stress from the numerical analysis result of prototype model was higher than that from scaled model due to different stiffness ratios between steel and concrete. However, the probability of failure for scaled model was higher than that for prototype model because failure criteria for scaled model was down due to similarity law. Also it was evaluated that probability of failure by using log normal standard deviation of response stresses by spectrum matched accelerograms was more reliable than probability of failure by using existing coefficient of variation normally used.
An austenitic stainless steel canister functions as a containment barrier for spent nuclear fuel and radioactive materials. The canister on the spent fuel storage system near the coastal area has several welding lines in the wall and lid, which have high residual tensile stresses after welding procedure. Interaction between austenitic stainless steel and chloride environment from a sea forms a detrimental condition causing chloride induced stress corrosion cracking (CISCC) in the canister. The South Korea is concerned with the dry storage of high-level spent nuclear fuel and radioactive wastes to be built on the site of a nuclear power plant. The importance of aging management has recently emerged for mitigating CISCC of dry storage canisters. When a corrosive pit is created by a localized corrosion in a sea water atmosphere, it initiates and grows as CISCC crack. Surface stress improvement works by inducing plastic strain which results in elastic relaxation that generates residual compressive stress. Surface stress improvement methods such as roller burnishing process can effectively mitigate the potential for CISCC of the canister external surfaces. The generation of compressive stress layer can inhibit the transition to cracking initiation. In this study, a flat roller burnishing process was applied as a prevention technology to CISCC of stainless steel canisters. Roller burnishing process parameters have been selected for 1:3 scale canister model having a diameter of 600 mm, a length of 1,000 mm and a thickness of 10 mm on the basis of the burnishing conditions available to control residual tensile stress of austenitic stainless steel plate specimens. The surface roughness of the scaled canister model was investigated using a surface roughness measurement equipment after roller burnishing treatment. The surface residual stresses of the scaled canister model were measured by a hole drilling contour method attached with strain gauge. The burnishing test results showed that the surface roughness of the scaled canister model was considerably improved with flat rollers having the tip width of 4 mm. The surface of the scaled canister model had significant residual compressive stress after burnishing treatment. The roller burnished canister with good surface roughness could reduce the number of crack initiation sites and the residual compressive stress formed on the welded surface might prevent the crack initiation by reducing tensile residual stress in the weld zone, finally leads to CISCC resistance.
Korea Hydro & Nuclear Power (KHNP) is currently developing a vertical concrete dry storage module for the dry storage of used nuclear fuel within nuclear power plants. This module is designed with a structure consisting of cylinders, which can block the ingress of external air, thereby preventing Chloride-Induced Stress Corrosion Cracking (CISCC). However, due to the presence of these cylinder structures, unlike conventional dry storage systems, it cannot directly dissipate heat to the external atmosphere, making thermal evaluation an important issue. The SF dry storage module being developed by KHNP is a massive concrete structure of approximately 20 m × 10 m × 7 m in size, employing a vertical storage system. To demonstrate the safety of such a large structure, there is no alternative to conducting experiments with scaled-down models. Furthermore, according to NUREG-2215 Section 5.5.4, it is explicitly mentioned that design-verification testing can be performed using scaled-down models. In this paper, a 1/4 scaled-down model was constructed to perform thermal performance verification experiments, and the effectiveness of this model was analyzed using Computational Fluid Dynamics (CFD) methods. The analysis results indicated that there was not a significant difference in terms of maximum concrete temperature and air outlet temperature. However, a considerable difference was observed in the canister surface temperature. Therefore, it is concluded that careful consideration of natural convection heat transfer is necessary for the full application of the scaled-down model.