Development and Validation of the 3-D Computational Fluid Dynamics Model for CANDU-6 Moderator Temperature Predictions

a b s t r a c t A Q1 numerical calculation with the commercial computational fluid dynamics code CFX-14.0 was conducted for a test facility simulating the Canadian deuterium uranium moderator thermalehydraulics. Two kinds of moderator thermalehydraulic tests at Stern Laboratories Inc. were performed in the full geometric configuration of the Canadian deuterium uranium moderator circulating vessel, which is called a calandria tank, housing a matrix of horizontal rod bundles simulating calandria tubes. The first of these tests is the pressure drop measurement of a cross flow in the horizontal rod bundles. The other is the local temperature measurement on the cross section of the horizontal cylinder vessel simulating the calandria system. In the present study, the full geometric details of the calandria tank are incorporated in the grid generation of the computational domain to which the boundary conditions for each experiment are applied. The numerical solutions are reviewed and compared with the available test data.

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“…Yoon et al [10] applied this pressure drop model into the commercial CFD code, CFX-4, and conducted a 3D calculation for the experiments at SLI.…”

Section: Q2mentioning

confidence: 99%

Computational fluid dynamics analysis of the Canadian deuterium uranium moderator tests at the Stern Laboratories Inc.

Kim

Chang

2015

Nuclear Engineering and Technology

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“…In fact, these types of calculations provide only average values of flow velocities and temperatures and do not give any information about local flow variables near tube solid walls, which are necessary to implement accurate heat transfer calculations. Along this line of thinking, the CFX commercial CFD code was applied with the porous media approach using segregated (Yoon et al, 2004 and2006) and coupled solvers (Yoon and Park, 2008) to simulate Calandria type experiments. Simulations were enhanced by Kim et al (2006) who used FLUENT to calculate moderator's flow across all calandria tubes.…”

Section: Introductionmentioning

confidence: 99%

“…Simulations were enhanced by Kim et al (2006) who used FLUENT to calculate moderator's flow across all calandria tubes. Yoon et al (2004 and2006) and Yoon and Park (2008) employed frictional pressure loss data collected for incompressible flows along in-line and staggered tube bundles to validate distributed hydraulic resistances. The experiments, performed at the Stern laboratories (Hadaller et al, 1996) used a quarter scale test section to simulate an axial slice of a CANDU-6 calandria vessel.…”

Section: Introductionmentioning

confidence: 99%

Moderator Flow Simulation Around Calandria Tubes of Candu-6 Nuclear Reactors

Teyssedou

Necciari

Reggio

et al. 2014

Engineering Applications of Computational Fluid Mechanics

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CFD simulations of cross-flows along in-line and staggered tube bundles which emulate those encountered in the calandria of CANDU-6 reactors are presented. The knowledge of external wall temperature distributions around calandria tubes is a major concern during normal and off-normal operating conditions of CANDU reactors. Calculations are performed using the FLUENT software with several turbulence models using segregated and Coupled algorithms. It is observed that κ-based models are able to reproduce mean velocities in staggered bundles. In most cases, the Coupled algorithm yields convergence even if it requires a longer computational time. Based on this work, the standard κ-ε model is recommended to perform this kind of simulations. Improved κ-ε models do not lead to better results while the κ-ω model predicts very well the physics only around the first row but it is unable to predict the flow around tubes located far downstream in the bundle.

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“…The CFX commercial CFD code was applied with the porous media approach using segregated (Yoon et al, 2004(Yoon et al, , 2006 and coupled solvers (Yoon and Park, 2008) to simulate Calandria type experiments.…”

Section: Literature Surveymentioning

confidence: 99%

CFD simulations of moderator flow inside Calandria of the Passive Moderator Cooling System of an advanced reactor

Pal

Kumar

Joshi

et al. 2015

Nuclear Engineering and Design

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Development and Validation of the 3-D Computational Fluid Dynamics Model for CANDU-6 Moderator Temperature Predictions

Cited by 23 publications

References 1 publication

Computational fluid dynamics analysis of the Canadian deuterium uranium moderator tests at the Stern Laboratories Inc.

Computational fluid dynamics analysis of the Canadian deuterium uranium moderator tests at the Stern Laboratories Inc.

Moderator Flow Simulation Around Calandria Tubes of Candu-6 Nuclear Reactors

CFD simulations of moderator flow inside Calandria of the Passive Moderator Cooling System of an advanced reactor

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