Experimental research on vertical mechanical performance of embedded through-penetrating steel-concrete composite joint in high-temperature gas-cooled reactor pebble-bed module
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(Reactor Pressure Vessel). The steel corbel is integrally embedded into the reactor-cabin wall through eight a...
| Main Authors: | , , , , |
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| Format: | Article |
| Language: | English |
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Elsevier
2022-01-01
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| Series: | Nuclear Engineering and Technology |
| Subjects: | |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573321004162 |
| _version_ | 1818976013990756352 |
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| author | Peiyao Zhang Quanquan Guo Sen Pang Yunlun Sun Yan Chen |
| author_facet | Peiyao Zhang Quanquan Guo Sen Pang Yunlun Sun Yan Chen |
| author_sort | Peiyao Zhang |
| collection | DOAJ |
| description | 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(Reactor Pressure Vessel). The steel corbel is integrally embedded into the reactor-cabin wall through eight asymmetrically arranged pre-stressed high-strength bolts, achieving the different path transmission of shear force and moment. The vertical monotonic loading test of two specimens is conducted. The results show that the failure mode of the joint is bolt fracture. There is no prominent yield stage in the whole loading process. The stress of bolts is linearly distributed along the height of corbel at initial loading. As the load increases, the height of neutral axis of bolts gradually decreases. The upper and lower edges of the wall opening contact the corbel plate to restrict the rotation of the corbel. During the loading, the pre-stress of some bolts decreases. The increase of the pre-stress strength ratio of bolts has no noticeable effect on the structure stiffness, but it reduces the ultimate bearing capacity of the joint. A simplified calculation model for the elastic stage of the joint is established, and the estimation results are in good agreement with the experimental results. |
| first_indexed | 2024-12-20T16:05:06Z |
| format | Article |
| id | doaj.art-5c0abf22edeb4b5d83719ac9c599643e |
| institution | Directory Open Access Journal |
| issn | 1738-5733 |
| language | English |
| last_indexed | 2024-12-20T16:05:06Z |
| publishDate | 2022-01-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Engineering and Technology |
| spelling | doaj.art-5c0abf22edeb4b5d83719ac9c599643e2022-12-21T19:34:11ZengElsevierNuclear Engineering and Technology1738-57332022-01-01541357373Experimental research on vertical mechanical performance of embedded through-penetrating steel-concrete composite joint in high-temperature gas-cooled reactor pebble-bed modulePeiyao Zhang0Quanquan Guo1Sen Pang2Yunlun Sun3Yan Chen4School of Transportation Science and Engineering, Beihang University, No.37 Xueyuan Road, Haidian District, Beijing, 100191, ChinaSchool of Transportation Science and Engineering, Beihang University, No.37 Xueyuan Road, Haidian District, Beijing, 100191, ChinaResearch and Development Center, Beijing Building Research Institute Co. Ltd of CSCEC, No.1 Xinhua Road, Fengtai District, Beijing, 100076, China; Corresponding author.Chinergy Technology Co. Ltd, No. 26 Zhongguancun Software Park, Haidian District, Beijing, 100193, ChinaChinergy Technology Co. Ltd, No. 26 Zhongguancun Software Park, Haidian District, Beijing, 100193, ChinaThe 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(Reactor Pressure Vessel). The steel corbel is integrally embedded into the reactor-cabin wall through eight asymmetrically arranged pre-stressed high-strength bolts, achieving the different path transmission of shear force and moment. The vertical monotonic loading test of two specimens is conducted. The results show that the failure mode of the joint is bolt fracture. There is no prominent yield stage in the whole loading process. The stress of bolts is linearly distributed along the height of corbel at initial loading. As the load increases, the height of neutral axis of bolts gradually decreases. The upper and lower edges of the wall opening contact the corbel plate to restrict the rotation of the corbel. During the loading, the pre-stress of some bolts decreases. The increase of the pre-stress strength ratio of bolts has no noticeable effect on the structure stiffness, but it reduces the ultimate bearing capacity of the joint. A simplified calculation model for the elastic stage of the joint is established, and the estimation results are in good agreement with the experimental results.http://www.sciencedirect.com/science/article/pii/S1738573321004162High-temperature gas-cooled reactor pebble-bed module (HTR-PM)Embedded through-penetratingSteel-concrete composite jointHigh-strength boltMechanical performance |
| spellingShingle | Peiyao Zhang Quanquan Guo Sen Pang Yunlun Sun Yan Chen Experimental research on vertical mechanical performance of embedded through-penetrating steel-concrete composite joint in high-temperature gas-cooled reactor pebble-bed module Nuclear Engineering and Technology High-temperature gas-cooled reactor pebble-bed module (HTR-PM) Embedded through-penetrating Steel-concrete composite joint High-strength bolt Mechanical performance |
| title | Experimental research on vertical mechanical performance of embedded through-penetrating steel-concrete composite joint in high-temperature gas-cooled reactor pebble-bed module |
| title_full | Experimental research on vertical mechanical performance of embedded through-penetrating steel-concrete composite joint in high-temperature gas-cooled reactor pebble-bed module |
| title_fullStr | Experimental research on vertical mechanical performance of embedded through-penetrating steel-concrete composite joint in high-temperature gas-cooled reactor pebble-bed module |
| title_full_unstemmed | Experimental research on vertical mechanical performance of embedded through-penetrating steel-concrete composite joint in high-temperature gas-cooled reactor pebble-bed module |
| title_short | Experimental research on vertical mechanical performance of embedded through-penetrating steel-concrete composite joint in high-temperature gas-cooled reactor pebble-bed module |
| title_sort | experimental research on vertical mechanical performance of embedded through penetrating steel concrete composite joint in high temperature gas cooled reactor pebble bed module |
| topic | High-temperature gas-cooled reactor pebble-bed module (HTR-PM) Embedded through-penetrating Steel-concrete composite joint High-strength bolt Mechanical performance |
| url | http://www.sciencedirect.com/science/article/pii/S1738573321004162 |
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