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- 저자 : Peiyao Zhang (검색결과 1 건)
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Peiyao Zhang,Quanquan Guo,Sen Pang,Yunlun Sun,Yan Chen 한국원자력학회 2022 Nuclear Engineering and Technology Vol.54 No.1
The high-temperature gas-cooled reactor pebble-bed module project is the first commercial Generation-IV NPP(Nuclear Power Plant) in China. A new joint is used for the vertical support of RPV(ReactorPressure Vessel). The steel corbel is integrally embedded into the reactor-cabin wall through eightasymmetrically arranged pre-stressed high-strength bolts, achieving the different path transmission ofshear force and moment. The vertical monotonic loading test of two specimens is conducted. The resultsshow that the failure mode of the joint is bolt fracture. There is no prominent yield stage in the wholeloading process. The stress of bolts is linearly distributed along the height of corbel at initial loading. Asthe load increases, the height of neutral axis of bolts gradually decreases. The upper and lower edges ofthe wall opening contact the corbel plate to restrict the rotation of the corbel. During the loading, thepre-stress of some bolts decreases. The increase of the pre-stress strength ratio of bolts has no noticeableeffect on the structure stiffness, but it reduces the ultimate bearing capacity of the joint. A simplifiedcalculation model for the elastic stage of the joint is established, and the estimation results are in goodagreement with the experimental results
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