본 연구에서는 원전 주제어실의 3차원 층 지진격리시스템에 대한 지진동 저감성능과 적용성을 평가하기 위해서 실험연구를 수행하였다. 3차원 층 지진격리시스템에 적용하기 위해서 마찰진자시스템과 에어 스프링을 설계하고 제작하였다. 제어 캐비닛과 액세스 플로어, 격자 프레임, 4개의 마찰진자와 에어 스프링으로 구성된 원전 주제어실 부분 실험모형을 2종류 제작하여 층 지진격리시스템의 원전 적용성을 평가하였다. 실험을 위해서 원전 주제어실의 운전기준지진(OBE)과 안전정지지진(SSE)의 수직방향, 수평방향 층 응답 스펙트럼을 이용하여 인공지진 시간이력을 만들어서 진동대 실험에 사용하였다. 입력지진에 대한 실험모형의 지진응답은 비 지진격리에 비해 3차원 층 지진격리시스템을 적용한 경우, 우수한 지진동 저감특성을 나타냈다

본 연구에서는 국내 원전에서 기기 정착을 위하여 가장 널리 적용되는 직매형 앵커기초를 대상으로 앵커기초의 인장 설계기준에 대한 적정성을 검토하기 위하여 수치해석이 수행되었다. 본 연구에서 수치해석모형에 적용된 파괴기준으로서 콘크리트와 같은 유사 취성재료에는 Microplane모형이, 앵커볼트와 같은 연성재료에는 탄성-완전 소성모형이 적용되었다. 그리고, 균열 발생현상을 모사하기 위하여 분산균열모형을 채택하였다. 개발된 수치해석모형은 다양한 경우의 실증시험결과를 근거로 신뢰성이 검증되었으며, 검증된 수치해석모형과 앵커볼트의 유효매입깊이를 변수로 한 다양한 경우에 대한 수치해석을 통하여 직매형 앵커기초의 인장설계기준으로서 적용이 가능한 ACI 349 Code와 CEB-FIP Code가 평가되었고, 그 보수성이 확인되었다.

전단파속도가 1,050m/sec 이하인 경우의 기초지반에 대한 내진해석에서는 지반-구조물 상호작용해석이 반드시 수행되어야 하며, 이러한 기초지반에서는 강지진동 작용시 지반의 비선형성이 현저하게 나타나므로 내진해석시 지반의 비선형성은 필수적으로 고려되어야 한다. 따라서, 본 연구에서는 입력지진동에 따른 지반의 비선형 거동을 평가하기 위한 방법으로서 기존의 수치해석적인 방법에 비하여 평가절차가 단순하고 신뢰성이 높은 Downhole 지진계측자료에 의한 평가방법을 제안하였다. 대만 화련부지를 대상으로 본 연구에서 제안한 지반의 비선형성 평가방법에 대한 신뢰성을 검증한 결과, 기존의 SHAKE프로그램에 의한 평가결과 및 지진응답 계측결과에 잘 일치하는 높은 수준의 정확성을 보임으로써 그 신뢰성 및 가용성을 확인할 수 있었다.

In this study, experimental study on the missile impact behavior of the nuclear power plant SC(steel plate concrete) wall was carried out to set up the future direction for the reasonable design method development. Four set of actual impact test of the SC wall were conducted at the EMRTC site located in Socorro, New Mexico. Initial and residual velocity of the missile, strain and acceleration of the back plate, local failure mode and deformation size, etc. were measured to study the local failure behaviour of the specimens. Finally, the experimental results are compared with the local failure evaluation formula and future research direction for the refined design method of the SC wall was reviewed.

The polar crane module in the reactor containment building has been reviewed to reduce the construction period and the workload on high elevation. In this paper, a numerical analysis for a lifting lug of the polar crane module was performed to confirm the structural integrity of the lug. The numerical analysis was also performed to check the structural integrity of the polar crane module. In regards of installation process, the constructability of the polar crane module was reviewed as well. Consequently, it is concluded that the reduction of construction period is possible.

In this study, the investigation of the local damage evaluation method for the SC structure subjected to impact load was carried out. The conventional RC formula and SC formula to calculate wall thickness to prevent perforation were studied and compared. Finally, these results were compared with finite element analysis results using LS-Dyna, and the future direction to develop the reasonable local damage evaluation method of the NPP SC structure was suggested.

According to NEI 07-13 R8, in aircraft impact analysis for new plant design, global structural damage of the target structure can be evaluated analytically using one of the following methods of evaluation: 1) Force time-history analysis method. 2) Missile-target interaction analysis method. It depends on the availability of data on the dynamic characteristics and the intended level of detail of analysis. The purpose of this study is to evaluate the effect on the analytical results of the aircraft impact analysis method. Several impact analyses using various method were performed for the simplified external SC wall of the APR+ nuclear power plant structure.

The rebar module in the common basemat of the reactor containment building has developed to reduce the construction period. In this paper, three stages of concrete pouring were reviewed for the possible application of the rebar module. The lifting frame design was done to lift the rebar module and the construction simulation was done to check the interface in the construction process.

In this study, an experimental study to investigate the shear friction behavior of the SC Wall to RC slab connection was carried out. The maximum shear friction capacity and failure mode were examined, and the results were also compared with theoretical value. Finally, the results are to be used for the basic reference of the design guideline(draft) for the RC-SC connection.

Recently, SC(Steel plate concrete) structure has been widely used in the design of the nuclear power plant structure because of its construction efficiency. In this study, the structural design program for SC structure was developed in accordance with KEPIC-SNG to provide optimal design condition. Especially, to reduce unnecessary simple repeat work in the design process, the design automation function was extensively included. The developed program is consist of three different design module: wall, slab, and connection design module.

Construction period is one of the most important factors which influence on cost and quality in nuclear power plant construction. As part of continued efforts for the competent reactor type, the construction improvements such as application of mechanical rebar splice, optimum lift height for concrete placement and enlargement of liner plate module in the reactor building wall are developed to minimize the construction period. This study referred to knowledge and experiences from APR+(Advanced Power Reactor Plus) technical development. The proposed method can be applied to the APR+ in the near future.

The objective of this study is to assess the structural response and impact energy absorption characteristics of reinforced concrete (RC) and steel plate concrete (SC) barrier walls under missile impact loading considered in the design of NPP (nuclear power plant)'s facilities. The study considered the barrier wall response under external tornado-generated missiles (e.g., steel pipe and automobiles).

Construction period is one of the most important factors which influence on cost and quality in nuclear power plant construction. As part of continued efforts for the competent reactor type, a dome liner plate module in the reactor containment building is developed to minimize the construction period. This study referred to knowledge and experiences from APR+(Advanced Power Reactor Plus) technical development. The proposed method can be applied to the APR+ in the near future.

The objective of this study is to develop the reinforcing design method of the NPP (nuclear power plant)'s steel plate concrete (SC) wall for enhancement of impact resistance capacity under the aircraft and missile impact loading considered in the design of NPP's facilities. This study investigated the effects of the several parameters that can affect impact resistance capacity of SC wall using finite element analysis method.(e.g., thickness of concrete and steel plate, material strength of concrete and steel, and other reinforcing design method).