Transient Three-Dimensional Stability Analysis of Supercritical Water Reactor Rod Bundle Subchannels by a Computatonal Fluid Dynamics Code

2009 ◽  
Vol 131 (2) ◽  
Author(s):  
M. Sharabi ◽  
W. Ambrosini ◽  
S. He ◽  
Pei-Xue Jiang ◽  
Chen-Ru Zhao
Keyword(s):  
Fluid Dynamics ◽  
Supercritical Water ◽  
Density Wave ◽  
Three Dimensional ◽  
Heating Rates ◽  
Rod Bundles ◽  
Water Reactor ◽  
Rod Bundle ◽  
Computational Fluid Dynamics Cfd ◽  
Supercritical Water Reactor

The paper describes the application of computational fluid dynamics (CFD) in simulating density wave oscillations in triangular and square pitch rod bundles. The FLUENT code is used for this purpose, addressing typical conditions proposed for supercritical water reactor (SCWR) conceptual design. The RELAP5 code and an in-house 1D linear stability code are also adopted to compare the results for instability thresholds obtained by different techniques. Transient analyses are performed both by the CFD code and RELAP5, with increasing heating rates and constant pressure drop across the channel, up to the occurrence of unstable behavior. The obtained results confirm that the density wave mechanism is similar in rod bundle and in axisymmetric configurations.

Stability analysis of a square rod bundle sub-channel in supercritical water reactor

2013 ◽  
Author(s):  
Wang Hai-jun ◽  
You Ting ◽  
Zhang Lei ◽  
Gu Hong-fang ◽  
Luo Yu-shan ◽  
...  
Keyword(s):  
Stability Analysis ◽  
Supercritical Water ◽  
Water Reactor ◽  
Rod Bundle ◽  
Supercritical Water Reactor

Control Rod Withdrawal Analysis of the Supercritical Water Reactor-Fuel Qualification Test Facility in the LVR-15 Research Reactor

2015 ◽  
Vol 2 (1) ◽  
Author(s):  
Csaba Maráczy ◽  
György Hegyi ◽  
István Trosztel ◽  
Emese Temesvári
Keyword(s):  
Supercritical Water ◽  
Research Reactor ◽  
Three Dimensional ◽  
Reactor Fuel ◽  
Test Facility ◽  
Qualification Test ◽  
Control Rod ◽  
Water Reactor ◽  
Reactivity Coefficients ◽  
Supercritical Water Reactor

The aim of the supercritical water reactor-fuel qualification test (SCWR-FQT) Euratom-China collaborative project is to design an experimental facility for qualification of fuel for the supercritical water-cooled reactor. The facility is intended to be operated in the LVR-15 research reactor in the Czech Republic. The pressure tube of the FQT facility encloses four fuel rods that will operate in similar conditions to the evaporator of the HPLWR reactor. This article deals with the three-dimensional (3D) coupled neutronic-thermohydraulic steady-state and transient analysis of LVR-15 with the fueled loop. Conservatively calculated enveloping parameters (e.g., reactivity coefficients) were determined for the safety analysis. The control rod withdrawal analysis of the FQT facility with and without reactor SCRAM was carried out with the KIKO3D-ATHLET-coupled dynamic code.

Numerical Analysis to Investigate the Effects of Thermal-Hydraulic Instabilities on Deterioration Heat Transfer and Wall Temperature in the CANDU Supercritical Water Reactor

2015 ◽  
Vol 1 (4) ◽  
Author(s):  
Goutam Dutta ◽  
Chao Zhang ◽  
Jin Jiang
Keyword(s):  
Heat Transfer ◽  
Supercritical Water ◽  
Wall Temperature ◽  
Stability Boundary ◽  
Density Wave ◽  
Operating Regime ◽  
Maximum Temperature ◽  
Water Reactor ◽  
Heating Section ◽  
Supercritical Water Reactor

The present work analyzes the thermal-hydraulic behavior of the CANDU supercritical water reactor (SCWR) using a 1-D numerical model. The possibility of a static instability, the Ledinegg excursion, is investigated, which reveals it can occur only in a hypothetical condition, far from the proposed operating regime of the CANDU SCWR. The investigation demonstrates the possibility of density wave oscillations (DWOs), a dynamic instability, in the operating regime of the CANDU SCWR and its marginal stability boundary (MSB) is obtained. The phenomenon of the deterioration in heat transfer is observed, and the related investigation shows that the strong buoyancy effect is responsible for its appearance inside the heating section of the channel of the CANDU SCWR core. The MSB is found to be inadequate in determining the safe operating zone of the reactor because the wall temperature can exceed the allowable limit from metallurgical consideration. The investigations also determine the safe as well as stable zone where the CANDU SCWR should operate in order to avoid the maximum temperature limit and DWOs.

Transient 3D Stability Analysis of SCWR Rod Bundle Subchannels by a CFD Code

2008 ◽  
Author(s):  
M. Sharabi ◽  
W. Ambrosini ◽  
S. He ◽  
Pei-Xue Jiang ◽  
Chen-Ru Zhao
Keyword(s):  
Stability Analysis ◽  
Pressure Drop ◽  
Conceptual Design ◽  
Constant Pressure ◽  
Density Wave ◽  
Heating Rates ◽  
Rod Bundles ◽  
Rod Bundle ◽  
Density Wave Oscillations ◽  
Relap5 Code

The paper describes the application of CFD in simulating density wave oscillations in triangular and square pitch rod bundles. The FLUENT code is used for this purpose, addressing typical conditions proposed for SCWR conceptual design. The RELAP5 code and an in-house 1D linear stability code are also adopted to compare the results for instability thresholds obtained by different techniques. Transient analyses are performed both by the CFD code and RELAP5, with increasing heating rates and constant pressure drop across the channel, up to the occurrence of unstable behaviour. The obtained results confirm that the density wave mechanism is similar in rod bundle and in axisymmetric configurations.

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