Abstract:A new code, CFD-BWR [1], is being developed for the simulation of two-phase flow phenomena inside a BWR fuel bundle. These phenomena include coolant phase changes and multiple flow regimes which directly influence the coolant interaction with fuel assembly and, ultimately, the reactor performance. CFD-BWR is a specialized module built on the foundation of the commercial CFD code STAR-CD [2] which provides general two-phase flow modeling capabilities. New models describing the inter-phase mass, momentum, and en… Show more
“…The topology in each mesh cell is determined by two parameters, a void fraction (a g ) and a gradient of the void fraction (g ¼ djra g j). Tentner et al [12,13], Ioilev et al [14] and Ustinenko et al [15] have established a significant progress to verify and validate this approach. The interphase topology concept proposed by Tentner et al [13] was employed in the CUPID code to deal with the flow pattern change from the bubbly flow to the churn and mist flow.…”
For the analysis of transient two-phase flows in nuclear reactor components, a three-dimensional thermal hydraulics code, named CUPID, has been being developed. We simulated the downcomer boiling experiment (DOBO) experiment in two-dimensions using the CUPID code to evaluate its two-phase flow models and verify its applicability to the downcomer boiling analysis. The simulation result showed that it can reproduce the important characteristics of the downcomer boiling, such as a flow pattern change from a bubbly flow to churn and mist flows and a circulation of liquid accelerated by bubbles. The twophase flow models that require further improvement were identified as well for an enhanced prediction of the downcomer boiling.
“…The topology in each mesh cell is determined by two parameters, a void fraction (a g ) and a gradient of the void fraction (g ¼ djra g j). Tentner et al [12,13], Ioilev et al [14] and Ustinenko et al [15] have established a significant progress to verify and validate this approach. The interphase topology concept proposed by Tentner et al [13] was employed in the CUPID code to deal with the flow pattern change from the bubbly flow to the churn and mist flow.…”
For the analysis of transient two-phase flows in nuclear reactor components, a three-dimensional thermal hydraulics code, named CUPID, has been being developed. We simulated the downcomer boiling experiment (DOBO) experiment in two-dimensions using the CUPID code to evaluate its two-phase flow models and verify its applicability to the downcomer boiling analysis. The simulation result showed that it can reproduce the important characteristics of the downcomer boiling, such as a flow pattern change from a bubbly flow to churn and mist flows and a circulation of liquid accelerated by bubbles. The twophase flow models that require further improvement were identified as well for an enhanced prediction of the downcomer boiling.
“…These models have been described in Refs. [1,2] and will be briefly reviewed in this section of the paper. The boiling model was recently expanded to include conjugate heat transfer so that the complete heat transfer system, including the heat conduction in the fuel and cladding, can be studied.…”
Section: Overview Of Two-phase Modelsmentioning
confidence: 99%
“…The details of the boiling model and the wall heat partitioning model can be found in Refs. [1][2][3][4]. In coupling the flow analysis with neutronics, temperatures of the fuel the cladding of the fuel pins must be determined together with the fluid temperatures as a conjugate heat transfer (CHT) problem.…”
“…The transitional topologies are the overlapping regions of two or three main topologies [18]. Tentner et al [20,21], Ioilev et al [22] and Ustinenko et al [23] have established significant progress to verify and validate this approach.…”
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