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- 저자 : Ma Shaopeng (검색결과 3 건)
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Spatial Distribution of Gusty Loads on a Rectangular Prism in Boundary Layer Flows
Jiadong Zeng,Mingshui Li,Shaopeng Li,Ruwei Ma 대한토목학회 2018 KSCE JOURNAL OF CIVIL ENGINEERING Vol.22 No.8
The pressure fluctuations acting on a stationary rectangular prism with cross configuration (2:1/1:2) are investigated by windtunnel testing. The synchronous surface pressures on the rigid model were measured in simulated atmospheric boundary layer flowand the unsteady forces were calculated by numerical integral of surface pressures. The effects of the wind fields and the model’s sideratio on the aerodynamic coefficients, spectral characteristics and spatial correlation of aerodynamic loading were investigated. Themain purpose of this study is to further analyze the spatial structure of the fluctuating wind loads acting on a rectangular prism as wellas to use the cross correlation coefficient and coherence function to explore their distribution trends. The results show that the alongwindgust loading is consistent with the longitudinal turbulence and the across-wind aerodynamic force is mainly induced by thevortex-shedding, recirculation and reattachment of separation shear layers on the lateral sides. In practical applications, the Strouhalnumber is approximately constant along the height. Extended empirical coherence models of the fluctuating along-wind and acrosswindloads are proposed with consideration to the effects of wind fields, the structure characteristics and dimensions of the prism andlength scale.
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Yi Yanan,Liu Guangyan,Xing Tongzhen,Lin Guang,Sun Libin,Shi Li,Ma Shaopeng 한국원자력학회 2020 Nuclear Engineering and Technology Vol.52 No.7
As a critical material in very/high-temperature gas-cooled reactors, graphite material directly affects the safety of the reactor core structures. Owing to the complex structures of graphite material in reactors, the material typically undergoes complex stress states. It is, therefore, necessary to study its mechanical properties, failure modes, and strength criteria under complex stress states so as to provide guidance for the core structure design. In this study, compressive failure tests were performed for graphite material under the condition of different confining pressures, and the effects of confining pressure on the triaxial compressive strength and Young's modulus of graphite material were studied. More specifically, graphite material based on the fracture surfaces and fracture angles, the graphite specimens were found to exhibit four types of failure modes, i.e., tension failure, shear-tension failure, tension-shear failure and shear failure, with increasing confining pressure. In addition, the Mohr strength envelope of the graphite material was obtained, and different strength criteria were compared. It showed that the parabolic MohrCoulomb criterion is more suitable for the strength evaluation for the graphite material.
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Study on failure mechanism of line contact structures of nuclear graphite
Jia Shigang,Yi Yanan,Wang Lu,Liu Guangyan,Ma Qinwei,Sun Libin,Shi Li,Ma Shaopeng 한국원자력학회 2022 Nuclear Engineering and Technology Vol.54 No.8
Line contact structures, such as the contact between graphite brick and graphite tenon, widely exist in high-temperature gas-cooled reactors. Due to the stress concentration effect, the line contact area is one of the dangerous positions prone to failure in the nuclear reactor core. In this paper, the failure mechanism of line contact structures composed of IG11 nuclear graphite column and brick were investigated by means of experiment and finite element simulation. It was found that the failure process mainly includes three stages: firstly, the damage accumulation in nuclear graphite material led to the characteristic yielding of the line contact structure, but no macroscopic failure can be observed at this stage; secondly, the stresses near the contact area met Mohr failure criterion, and a crack initiated and propagated laterally in the contact zone, that is, local macroscopic failure occurred at this stage; finally, a second crack initiated in the contact area and developed in to a Y-shape, resulting in the final failure of the structure. This study lays a foundation for the structural design and safety assessment of hightemperature gas-cooled reactors
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