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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. Numerical analysis is carried out to identify the appropriateness of the design codes that is available for the tensile design of fastening system at Nuclear Power Plant (NPP) in this study. This study is intended for the cast-in-place anchor that is widely used for the fastening of equipment in Korean NPPs. The microplane model and the elastic-perfectly plastic model are employed for the quasi-brittle material like concrete and for the ductile material like anchor bolt as constitutive model for numerical analysis and smeared crack model is employed to simulate the clack and damage phenomena. The developed numerical model is verified on a basis of the various test data of cast-in-place anchor. The appropriateness of both ACI 349 Code and CEB-FIP Code is evaluated for the tensile design of cast-in-place anchor and it is proved that both design codes give a conservative results for real tensile capacity of cast-in-place anchor.
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.
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.
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.
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.
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.
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).
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.
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.
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.