THREE DIMENSIONAL THERMAL HYDRAULIC COUPLING METHOD ON PWR STEAM GENERATOR USING CFD METHOD
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- Zhao Xiaohan
- Xi’an Jiaotong University School of Nuclear Science and Technology
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- Wang Mingjun
- Xi’an Jiaotong University School of Nuclear Science and Technology
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- Tian Wenxi
- Xi’an Jiaotong University School of Nuclear Science and Technology
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- Su G.H.
- Xi’an Jiaotong University School of Nuclear Science and Technology
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- QIU Suizheng
- Xi’an Jiaotong University School of Nuclear Science and Technology
抄録
Steam generator (SG) is a key equipment for the PWR system which play the role of energy exchanger hub for removing fission energy from the reactor safely. The operational status of the SG is related to the safety of the reactor. The structure of SG is extraordinary complex and the coolant flow state is also complicated which because the coolant in the primary side is forced convection but two phase flow in the secondary side. To deeply reveal the three-dimensional heat transfer characteristics of the whole SG, a three dimensional thermal hydraulic coupling method is established based on the porous media method and CFD software in this research. The geometry of the SG is simplified to some extent at the first step in this research which both sides of the tube bundle zone are considered as a unified volume based on the porous media method. The three dimensional energy coupling function between the primary and the secondary side is achieved through adding a functional user defined function to the simulation model. Finally the thermalhydraulic characteristics about the primary side and the secondary side are obtained respectively. The success of the coupling simulation about SG in this research can prove the feasibility of this method and can be a good foundation for the research on the thermal hydraulic characteristics about more complex SG prototype in Nuclear Power Plant (NPP).
収録刊行物
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- Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE
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Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE 2019.27 (0), 2322-, 2019
一般社団法人 日本機械学会
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詳細情報 詳細情報について
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- CRID
- 1390283659834321152
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- NII論文ID
- 130007773881
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- ISSN
- 24242934
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- 本文言語コード
- en
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- データソース種別
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- JaLC
- Crossref
- CiNii Articles
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- 抄録ライセンスフラグ
- 使用不可