Development of a new full-range critical flow model based on non-homogeneous non-equilibrium model

Abstract Critical flow has significant impact on the reactor safety. Critical flow models are considered as an important module in all system thermal–hydraulic (STH) codes, with several optional models. But each model has its own scope of application. Consequently, the STH simulation results largely dependent on the model choice, i.e. on the user effect. A full-range critical flow model may be used to deal with this issue. The aim of this work was to develop a full-range 6-equation critical flow model with higher accuracy and plug it into ATHLET. The model was validated in Henry tests. The results show that the new model could predict mostly within the error band ±20%, better than other models of ATHLET. To verify the ability of ATHLET with the new model, it was applied to several Marviken full scale critical flow tests in transient, showing better (or at least comparable) results than before.

[1]  L. Friedel.  Improved Friction Pressure Drop Correlation for Horizontal and Vertical Two-Phase Pipe Flow , 1979 .

[2]  S. Kabanikhin.  Definitions and examples of inverse and ill-posed problems , 2008 .

[3]  Alfio Quarteroni,et al.  Scientific Computing with MATLAB and Octave (Texts in Computational Science and Engineering) , 2006 .

[4]  M. Avramova,et al.  Challenges in coupled thermal-hydraulics and neutronics simulations for LWR safety analysis , 2007 .

[5]  N. Zuber.  ON THE DISPERSED TWO-PHASE FLOW IN THE LAMINAR FLOW REGIME. , 1964 .

[6]  Haijun Wang,et al.  Critical flow leakage of a vapour-liquid mixture from sub-cooled water: Nucleation boiling study , 2020 .

[7]  Jean-Marie Seynhaeve,et al.  Benchmark of Delayed Equilibrium Model (DEM) and classic two-phase critical flow models against experimental data , 2017 .

[8]  A. Ruggles,et al.  The propagation of pressure perturbations in bubbly air/water flows , 1988 .

[9]  O. Oluwole,et al.  Comparative Study of Matlab ODE Solvers for the Korakianitis and Shi Model , 2017 .

[10]  Xiang Yu,et al.  Modeling the full-range thermal-hydraulic characteristics and post-dryout deviation from thermodynamic equilibrium in once-through steam generators , 2017 .

[11]  Francesco Saverio D'Auria,et al.  Thermal-Hydraulic System Codes in Nulcear Reactor Safety and Qualification Procedures , 2008 .

[12]  J. Thome,et al.  Convective Boiling and Condensation , 1972 .

[13]  Jean-Marie Seynhaeve,et al.  A Model for Choked Flow-through Cracks With Inlet Subcooling , 1993 .

[14]  H. J. Richter,et al.  Separated two-phase flow model: application to critical two-phase flow , 1983 .

[15]  Yeon-Sik Kim.  A proposed correlation for critical flow rate of water flow , 2015 .

[16]  D. Chisholm,et al.  Pressure gradients due to friction during the flow of evaporating two-phase mixtures in smooth tubes and channels , 1973 .

[17]  M. McLinden,et al.  NIST Standard Reference Database 23: Reference Fluid Thermodynamic and Transport Properties-REFPROP, Version 8.0 , 2007 .

[18]  J. M. Healzer,et al.  Critical flow data review and analysis , 1982 .

[19]  Xu Cheng,et al.  Studies on the criterion for choking process in two-phase flow , 2021 .

[20]  G. Wallis.  One Dimensional Two-Phase Flow , 1969 .

[21]  R. Henry.  A Study of One and Two Component, Two Phase Critical Flows at Low Qualities , 2013 .

[22]  J. Thom,et al.  Prediction of pressure drop during forced circulation boiling of water , 1964 .

[23]  Haihua Zhao,et al.  RELAP-7 Theory Manual , 2015 .

[24]  Xu Cheng,et al.  Sensitivity analysis of thermal-hydraulic models based on FFTBM-MSM two-layer method for PKL IBLOCA experiment , 2020 .

[25]  Yeon-Sik Kim.  Critical flow maps using an extended Henry–Fauske model , 2015 .

[26]  F. Dobran.  Nonequilibrium Modeling of Two-Phase Critical Flows in Tubes , 1987 .

[27]  Donald E. Carlson,et al.  Perspectives on understanding and verifying the safety terrain of modular high temperature gas-cooled reactors , 2016 .

[28]  E. Wacholder,et al.  A two-fluid model for critical flashing flows in pipes , 1993 .

[29]  H. Glaeser,et al.  Verification and validation of system thermal-hydraulic computer codes, scaling and uncertainty evaluation of calculated code results , 2017 .

[30]  Xu Cheng,et al.  Optimization of the Nodalization of Nuclear System Thermal-Hydraulic Code Applied On PKL Benchmark , 2021 .

[31]  J. Verwer,et al.  Stability of Runge-Kutta Methods for Stiff Nonlinear Differential Equations , 1984 .

[32]  Xu Cheng,et al.  Analysis of two phase critical flow with a non-equilibrium model , 2021 .

[33]  Paul David Bayless.  RELAP5-3D Developmental Assessment. Comparison of Version 4.3.4i on Linux and Windows , 2015 .

[34]  Robert E. Henry,et al.  The Two-Phase Critical Flow of One-Component Mixtures in Nozzles, Orifices, and Short Tubes , 1971 .

[35]  Neill P. Taylor,et al.  Safety and licensing of nuclear facilities for fusion , 2015, 2015 IEEE 26th Symposium on Fusion Engineering (SOFE).

[36]  L. Shampine,et al.  Numerical Solution of Ordinary Differential Equations. , 1995 .

[37]  Richard R. Schultz,et al.  RELAP5/MOD3 code manual: Summaries and reviews of independent code assessment reports. Volume 7, Revision 1 , 1996 .

[38]  Richard R. Schultz,et al.  RELAP5/MOD3 Code Manual , 1992 .

[39]  Ezra Elias,et al.  Two-phase critical flow , 1994 .

[40]  David J. Jeffrey,et al.  Hydrodynamic interaction between gas bubbles in liquid , 1976, Journal of Fluid Mechanics.