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RISS 인기검색어
- 검색키워드
- 저자 : Amir Hossein Kamalinia (검색결과 2 건)
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Kamalinia Amir Hossein,Rabiee Ataollah 한국원자력학회 2023 Nuclear Engineering and Technology Vol.55 No.12
A correct understanding of vibration-based degradation is crucial from the standpoint of maintenance for Steam Generators (SG) as crucial mechanical equipment in nuclear power plants. This study has established a novel approach to developing a model for investigating tube bundle degradation according to crack growth caused by two-phase Flow-Induced Vibration (FIV). An important step in the approach is to calculate the two-phase flow field parameters between the SG tube bundles in various zones using the porous media model to determine the velocity and vapor volume fraction. Afterward, to determine the vibration properties of the tube bundles, the Fluid-Solid Interaction (FSI) analysis is performed in eighteen thermal-hydraulic zones. Tube bundle degradation based on crack growth using the sixteen most probable initial cracks and within each SG thermal-hydraulic zone is performed to calculate useful lifetime. Large Eddy Simulation (LES) model, Paris law, and Wiener process model are considered to model the turbulent crossflow around the tube bundles, simulation of elliptical crack growth due to the vibration characteristics, and estimation of SG tube bundles degradation, respectively. The analysis shows that the tube deforms most noticeably in the zone with the highest velocity. As a result, cracks propagate more quickly in the tube with a higher height. In all simulations based on different initial crack sizes, it was observed that zone 16 experiences the greatest deformation and, subsequently, the fastest degradation, with a velocity and vapor volume fraction of 0.5 m/s and 0.4, respectively.
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Two-Phase Flow Field Simulation of Horizontal Steam Generators
Ataollah Rabiee,Amir Hossein Kamalinia,KAMAL HADAD 한국원자력학회 2017 Nuclear Engineering and Technology Vol.49 No.1
The analysis of steam generators as an interface between primary and secondary circuitsin light water nuclear power plants is crucial in terms of safety and design issues. VVER-1000 nuclear power plants use horizontal steam generators which demand a detailedthermal hydraulics investigation in order to predict their behavior during normal andtransient operational conditions. Two phase flow field simulation on adjacent tube bundlesis important in obtaining logical numerical results. However, the complexity of the tubebundles, due to geometry and arrangement, makes it complicated. Employment of porousmedia is suggested to simplify numerical modeling. This study presents the use of porousmedia to simulate the tube bundles within a general-purpose computational fluid dynamicscode. Solved governing equations are generalized phase continuity, momentum,and energy equations. Boundary conditions, as one of the main challenges in thisnumerical analysis, are optimized. The model has been verified and tuned by simpletwo-dimensional geometry. It is shown that the obtained vapor volume fraction near thecold and hot collectors predict the experimental results more accurately than in previousstudies.
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