Analytical and Computational Analysis of Flow Splitting in Multiple, Parallel Channels Systems  

Analytical and Computational Analysis of Flow Splitting in Multiple, Parallel Channels Systems

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作  者:Alejandro I. Lazarte J. C. Ferreri Alejandro I. Lazarte;J. C. Ferreri(Autoridad Regulatoria Nuclear, Buenos Aires, Argentina;Academia Nacional de Ciencias de Buenos Aires, Buenos Aires, Argentina)

机构地区:[1]Autoridad Regulatoria Nuclear, Buenos Aires, Argentina [2]Academia Nacional de Ciencias de Buenos Aires, Buenos Aires, Argentina

出  处:《World Journal of Nuclear Science and Technology》2016年第3期170-190,共22页核科学与技术国际期刊(英文)

摘  要:Previous analytical results on flow splitting are generalized to consider multiple boiling channels systems. The analysis is consistent with the approximations usually adopted in the use of systems codes (like RELAP5 and TRACE5, among others) commonly applied to perform safety analyses of nuclear power plants. The problem is related to multiple, identical, parallel boiling channels, connected through common plena. A theoretical model limited in scope explains this flow splitting without reversal. The unified analysis performed and the confirmatory computational results found are summarized in this paper. New maps showing the zones where this behavior is predicted are also shown considering again twin pipes. Multiple pipe systems have been found not easily amenable for analytical analysis when dealing with more than four parallel pipes. However, the particular splitting found (flow along N pipes dividing in one standalone pipe flow plus N -1 identical pipe flows) has been verified up to fourteen pipes, involving calculations in systems with even and odd number of pipes using the RELAP5 systems thermal-hydraulics code.Previous analytical results on flow splitting are generalized to consider multiple boiling channels systems. The analysis is consistent with the approximations usually adopted in the use of systems codes (like RELAP5 and TRACE5, among others) commonly applied to perform safety analyses of nuclear power plants. The problem is related to multiple, identical, parallel boiling channels, connected through common plena. A theoretical model limited in scope explains this flow splitting without reversal. The unified analysis performed and the confirmatory computational results found are summarized in this paper. New maps showing the zones where this behavior is predicted are also shown considering again twin pipes. Multiple pipe systems have been found not easily amenable for analytical analysis when dealing with more than four parallel pipes. However, the particular splitting found (flow along N pipes dividing in one standalone pipe flow plus N -1 identical pipe flows) has been verified up to fourteen pipes, involving calculations in systems with even and odd number of pipes using the RELAP5 systems thermal-hydraulics code.

关 键 词:Multiple Parallel Boiling Channels Systems Asymmetric Splitting Flow Verification of Codes Systems Thermal-Hydraulics Codes Nuclear Engineering 

分 类 号:O35[理学—流体力学]

 

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