Large Eddy Simulation for an inherent boron dilution transient

Abstract The present paper focuses on the validation and applicability of large eddy simulation (LES) to analyze the transport and mixing in the reactor pressure vessel (RPV) during an inherent boron dilution transient (BDT) scenario. Extensive validation data comes from relevant integral tests performed in the scaled ROCOM experimental facility. The modeling of sub-grid-scales is based on the WALE model. A fully conformal polyhedral grid of about 15 million cells is constructed to capture all details in the domain, including the complex structures of the lower-plenum. Detailed qualitative and quantitative validations are performed by following a systematic multi-step validation methodology. Qualitative comparisons to the experimental data in the cold legs, downcomer and the core inlet showed good predictions by the LES model. Minor deviations seen in the quantitative comparisons are rigorously quantified. A key parameter which is affecting the core neutron kinetics response is the value of highest deborated slug concentration that occurs at the core inlet during the transient. Detailed analyses are made at the core inlet to evaluate not only the value of the maximum slug concentration, but also the location and the time at which it occurs during the transient. The relative differences between the ensemble averaged experimental data and CFD predictions were within the range of relative differences seen within 10 different experimental realizations. For the studied scenario, the present LES results lend support to its reliability in consistently predicting the slug transport in the RPV.

[1]  Frank-Peter Weiss,et al.  Experimental Investigation of Coolant Mixing in the RPV of a PWR During Natural Circulation Conditions , 2004 .

[2]  Frank-Peter Weiss,et al.  Coolant mixing in a PWR - de-boration transients, steam line breaks and emergency core cooling injection - experiments and analyses , 2002 .

[3]  A. W. Vreman,et al.  Subgrid-modelling in LES of Compressible Flow , 1995 .

[4]  E.M.J. Komen,et al.  Application of large-eddy simulation to pressurized thermal shock: Assessment of the accuracy , 2011 .

[5]  Andreas Schaffrath,et al.  Validation of the CFD code fluent by post-test calculation of a density-driven ROCOM experiment , 2007 .

[6]  E.M.J. Komen,et al.  Application of large-eddy simulation to pressurized thermal shock problem: A grid resolution study , 2010 .

[7]  Soeren Kliem,et al.  Experiments at the mixing test facility ROCOM for benchmarking of CFD codes , 2008 .

[8]  B. Hemström,et al.  CFD simulation of the Vattenfall 1/5th-scale PWR model for boron dilution studies , 2008 .

[9]  F. Nicoud,et al.  Subgrid-Scale Stress Modelling Based on the Square of the Velocity Gradient Tensor , 1999 .

[10]  Frank-Peter Weiss,et al.  Boron dilution transients during natural circulation flow in PWR—Experiments and CFD simulations , 2008 .

[11]  E.M.J. Komen,et al.  Suitability of wall-functions in Large Eddy Simulation for thermal fatigue in a T-junction , 2010 .

[12]  Frank-Peter Weiss,et al.  Coolant Mixing in a Pressurized Water Reactor: Deboration Transients, Steam-Line Breaks, and Emergency Core Cooling Injection , 2003 .

[13]  Peter Gango Numerical boron mixing studies for Loviisa nuclear power plant , 1997 .

[14]  Soeren Kliem,et al.  Fluid mixing and flow distribution in a primary circuit of a nuclear pressurized water reactor—Validation of CFD codes , 2007 .

[15]  S. Benhamadouche,et al.  A synthetic-eddy-method for generating inflow conditions for large-eddy simulations , 2006 .

[16]  Thomas Höhne,et al.  Modeling of a buoyancy-driven flow experiment at the ROCOM test facility using the CFD codes CFX-5 and Trio_U , 2006 .

[17]  P. Quemere,et al.  Verification and validation considerations regarding the qualification of numerical schemes for LES for dilution problems , 2010 .

[18]  E.M.J. Komen,et al.  Application of Large-Eddy Simulation to Pressurized Thermal Shock Problem , 2009 .