Stability of supercritical fluid flow in a single-channel natural-convection loop

Chatoorgoon, Vijay

doi:10.1016/s0017-9310(00)00218-0

Cited by 122 publications

(31 citation statements)

References 3 publications

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“…Figure 8 shows the contour plot of the measured mass flow rates, also indicating the zone of instability (black line) and the reference line (black dashed line). Chatoorgoon [49] previously postulated that the onset of thermo-hydraulic instabilities in a supercritical loop was linked to the peak of the power flow-to-map:…”

Section: Linear Stabilitymentioning

confidence: 99%

“…For a simplified loop case he was able to show good agreement between this criterion and his own numerical code. However, Jain and Uddin [30] later showed that the results of Chatoorgoon [49] were not independent of the time step or the spatial discretisation. By using smaller time steps and a finer grid, Jain and Uddin [30] obtained a converged solution that showed a transition to instability before the mass flow peak is reached.…”

Section: Linear Stabilitymentioning

confidence: 99%

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Experimental study of the coupled thermo-hydraulic–neutronic stability of a natural circulation HPLWR

T’Joen

Rohde

2012

Nuclear Engineering and Design

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The HPLWR (High Performance Light Water Reactor) is the European concept design for a SCWR (SuperCritical Water Reactor). This unique reactor design consists of a three pass core with intermediate mixing plena. As the supercritical water passes through the core, it experiences a significant density reduction. This large change in density could be used as the driving force for natural circulation of the coolant, adding an inherent safety feature to this concept design. The idea of natural circulation has been explored in the past for boiling water reactors (BWR). From those studies, it is known that the different feedback mechanisms can trigger flow instabilities. These can be purely thermo-hydraulic (driven by the friction -mass flow rate or gravity -mass flow rate feedback of the system), or they can be coupled thermo-hydraulic -neutronic (driven by the coupling between friction, mass flow rate and power production). The goal of this study is to explore the stability of a natural circulation HPLWR considering the thermo-hydraulic -neutronic feedback. This was done through a unique experimental facility, DeLight, which is a scaled model of the HPLWR using Freon R23 as a scaling fluid. An artificial neutronic feedback was incorporated into the system based on the average measured density. To model the heat transfer dynamics in the rods, a simple first order model was used with a fixed time constant of 6 seconds. The results include the measurements of the varying decay ratio (DR) and frequency over a wide range of operating conditions. A clear instability zone was found within the stability plane, which seems to be similar to that of a BWR. Experimental data on the stability of a supercritical loop is rare in open literature, and these data could serve as an important benchmark tool for existing codes and models.

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Section: Linear Stabilitymentioning

confidence: 99%

Section: Linear Stabilitymentioning

confidence: 99%

Experimental study of the coupled thermo-hydraulic–neutronic stability of a natural circulation HPLWR

T’Joen

Rohde

2012

Nuclear Engineering and Design

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“…The experimental research work recently carried out by Xiong et al (2012) and several numerical studies (Chatoorgoon, 2001;Gómez et al, 2008;Jain and Rizwan-uddin, 2008;Ambrosini and Sharabi, 2008;Sharabi et al, 2008;Ambrosini, 2009;Zhao et al, 2011;T'Joen et al, 2011;Ambrosini, 2011;Ampomah-Amoako and Ambrosini, 2013;Xiong et al, 2013) confirmed the possibility of flow induced DWOs for various fluids operating at supercritical conditions. The out-of-phase mode of oscillations in two parallel channels at supercritical conditions were experimentally observed by Xiong et al (2012) and then, the study was followed by a numerical investigation (Xiong et al, 2013) using a 1-D thermalhydraulic (TH) model.…”

Section: Introductionmentioning

confidence: 78%

Analysis of parallel channel instabilities in the CANDU supercritical water reactor

Dutta

Zhang

Jiang

2015

Annals of Nuclear Energy

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“…Chatoorgoon (2001) analytically studied the flow instability of a simple rectangular open loop with supercritical water. Instability boundary was postulated to be at the peak point of the flow-power curve.…”

Section: Instability Studies Of Circulation Loop 23mentioning

confidence: 99%

Numerical Instability Study of Supercritical Water Flowing Upward in Two Heated Parallel Channels

Chatoorgoon

Ormiston

2017

Proceedings of the 20th Pacific Basin Nuclear Conference

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A three dimensional numerical investigation of supercritical water flowing upward in two heated parallel channels was developed using a RANS model in the Computational Fluid Dynamics (CFD) code ANSYS CFX. The standard k- turbulence model with scalable wall functions was adopted throughout this numerical study.The effects of spatial and temporal grid sizes on flow instability were studied first. Then oscillatory instabilities of nine experimental cases were predicted using the CFX code.For comparison purposes, Chatoorgoon"s 1-D non-linear SPORTS code was also used to determine the instability boundary. These new numerical results were compared with the experimental data and previous numerical results by other investigators.Additionally, the effects of changing the outlet plenum volume, the turbulent Prandtl number, the turbulence inlet conditions, the outlet K factor, the maximum iterations per time step in the transient analysis and the order of the transient scheme on the instability thresholds were examined.ii ACKNOWLEDGEMENTS

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Stability of supercritical fluid flow in a single-channel natural-convection loop

Cited by 122 publications

References 3 publications

Experimental study of the coupled thermo-hydraulic–neutronic stability of a natural circulation HPLWR

Experimental study of the coupled thermo-hydraulic–neutronic stability of a natural circulation HPLWR

Analysis of parallel channel instabilities in the CANDU supercritical water reactor

Numerical Instability Study of Supercritical Water Flowing Upward in Two Heated Parallel Channels

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