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Simulation on the thermal hydraulics of the coolant in a pebble bed reactor core by CFD

  • Xi'an Jiaotong University

科研成果: 书/报告/会议事项章节会议稿件同行评审

摘要

The 3-D physical and geometrical model of the water cooled pebble bed reactor (WCPBR) were built using the commercial software ProE and CFX, in which the thermal-hydraulic characteristics of the coolant were studied based on the computational fluid dynamics (CFD) in this work. The velocity field, temperature field and pressure distribution of the coolant are obtained and analyzed in the case of inter-pebble gap and direct contact and its effects on the core safety are also analyzed. In the case of inter-pebble gap, the maximum temperature of the pebble was found in the range of gap, two minima pressures and two maximum velocities were found at the contact points. In the direct contact case, two maximum temperatures were found at the contact points and the maximum velocity was found in the range of gap. From the results, it is evident that the direct contact case is closer to actual case.

源语言英语
主期刊名Proceedings of the 17th International Conference on Nuclear Engineering 2009, ICONE17
667-672
页数6
DOI
出版状态已出版 - 2009
活动17th International Conference on Nuclear Engineering, ICONE17 - Brussels, 比利时
期限: 12 7月 200916 7月 2009

出版系列

姓名International Conference on Nuclear Engineering, Proceedings, ICONE
4

会议

会议17th International Conference on Nuclear Engineering, ICONE17
国家/地区比利时
Brussels
时期12/07/0916/07/09

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