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- W2186832304 abstract "The knowledge on the structure and dynamical behavior of the two phase flow is important for a great number of processes, including the coolant behavior in a nuclear power reactor. Previous studies performed on gas liquid phase or in experimental devices specially designed for that purpose, have introduced theoretical models that describe the void fraction fluctuations in a two phase flow. Nevertheless, they only partially explained the measured effects or have a doubtful applicability. In this work, from data obtained from a BWR nuclear power plant, we apply different mathematical models in order to study the change of the intensity of the void fraction fluctuations along the channel. By comparing these models, we conclude that the bimodal two- phase flow model is a more realistic one for void fraction estimation. This model can be applied for high void fraction rate and converges to the Poisson model for low void fraction rate. The expected contribution of this work is, by means of a proper use of neutron signal analysis, to obtain a better understanding of the dynamics and structure of the two phase flow in a nuclear power reactor." @default.
- W2186832304 created "2016-06-24" @default.
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- W2186832304 date "2008-01-01" @default.
- W2186832304 modified "2023-09-24" @default.
- W2186832304 title "Void fraction fluctuations in two phase flow: theoretical models" @default.
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