Validation of Multiphase Flow Modeling in ANSYS CFD
|
|
- Amice Cobb
- 5 years ago
- Views:
Transcription
1 Validation of Multiphase Flow Modeling in ANSYS CFD Th. Frank, C. Lifante, A.D. Burns Head Funded CFD Development ANSYS Germany 2009 ANSYS, Inc. All rights reserved. 1 ANSYS, Inc. Proprietary
2 Outline Introduction MPF model validation for adiabatic air-water flows Polydisperse MPF model validation MUSIG model Bartolomej testcase (PWR) Lee testcase (BWR) Wall boiling with conjugate heat transfer (CHT) Summary & Outlook Courtesy by E. Krepper (FZD) 2009 ANSYS, Inc. All rights reserved. 2 ANSYS, Inc. Proprietary
3 ANSYS as Part of the German CFD Network in Nuclear Reactor Safety FZ Dresden- ANSYS FZ Karlsruhe Rossendorf Germany GRS Becker Technologies ThAI test facility International Guest Visitors AREVA TU München: TD, Nucl. Energy Univ. Applied Sciences Zittau-Görlitz: IPM Univ. Stuttgart: Nuclear Energy 2009 ANSYS, Inc. All rights reserved. 3 ANSYS, Inc. Proprietary
4 Methodology of CFD Model Development & Validation Experiment phys.-math. Model Complex Geometry 3d CFD Model Complex Flow Conditions Validation Combination with other Models 2009 ANSYS, Inc. All rights reserved. 4 ANSYS, Inc. Proprietary
5 Eulerian MPF Modeling - The Particle Model Mass weighted averaged conservation equations Mass, momentum, energy transport equations for each phase t t r r U k k k k k kl l 1 l k N k r r r P r U U U F I k k k k k k k k k k k Ik F F D F L F WL F TD F V M secondary drag lift wall turbulent mom. transfer lubrication dispersion virtual mass turbulence models for each phase (e.g. k- / k- SST model, 0-eq. disp. phase turb. Model) heat transfer equations for each phase with interfacial transfer closure interfacial i forces need empirical i closure high void fraction effects, bubble induced turbulence, etc ANSYS, Inc. All rights reserved. 5 ANSYS, Inc. Proprietary
6 Lift force, Wall lubrication force & turbulent dispersion Lift force: due to asymmetric wake and deformed asymmetric particle shape Tomiyama C L correlation F C r ( U U ) U C C (Re, Re, Eo) L L G L L G L Wall lubrication force: L L P surface tension prevents bubbles from approaching solid walls Antal, Tomiyama & Frank W.L.F. models F C r U U n n n WL wall G L rel rel W W W Turbulent dispersioni force: 2 C C wall W turbulent dispersion = action of turb. eddies via interphase drag F C r r 3 D tf P F TD F UF UP rp 4 dp rf rp rf (Eo, y/d ) FAD model by Burns et al. (ICMF 04) P 2009 ANSYS, Inc. All rights reserved. 6 ANSYS, Inc. Proprietary
7 Bubbly Flow Model Validation FZR MT-Loop and TOPFLOW Database TOPFLOW MT-Loop 2009 ANSYS, Inc. All rights reserved. 7 ANSYS, Inc. Proprietary
8 CFX Model Validation MT-Loop & TOPFLOW Test Matrix M01 experimental test series on MT-Loop evaluation based on air volume fraction profiles at L/D=59,2 (z=3.03m) from the sparger system - numerically investigated test case conditions finely disperse bubbly flow water velocity J_L [m/s] superficial bubbly flow with near wall void fraction maximum bubbly flow in the transition regime bubbly flow with void fraction maximum at pipe center bubbly bbl flow with void fraction maximum at pipe center, bimodal slug flow superficial air velocity J_G [m/s] 2009 ANSYS, Inc. All rights reserved. 8 ANSYS, Inc. Proprietary
9 Validation: Bubbly Flows Turbulent Dispersion Force k-eps + RPI TD (0.5) 300 3,00 k-eps + FAD TD. Air Volume Fraction 2,00 SST + RPI TD (0.5) SST + FAD TD Data Model improvement Norm. 1,00 0, Radius, mm 2009 ANSYS, Inc. All rights reserved. 9 ANSYS, Inc. Proprietary
10 Monodispersed Bubbly Flow MT-Loop Test Case FZR-019 FZD-019: J L =1.017 m/s J G =0.004 m/s J G d P =4.8 mm Grace drag Tomiyama lift T./A./F. Wall L. Force FAD Turb. Disp. SST turb. model Sato model t=0.002s 2210 Iterations n [-] d volume fractio normalize Experiment FZR Antal W.L.F., Grid Tomiyama W.L.F., Grid Frank W.L.F., Grid Radius [mm] 2009 ANSYS, Inc. All rights reserved. 10 ANSYS, Inc. Proprietary
11 Monodispersed Bubbly Flow MT-Loop Test Case FZR FZD-052: J L =1.017 m/s J G = m/s 4.0 J G d P =4.4 mm Grace drag Tomiyama lift T./A./F. Wall L. Force FAD Turb. Disp. SST turb. model normalized volume fraction [-] Experiment FZR-052 Antal W.L.F., Grid 2 Tomiyama W.L.F., Grid 2 Frank W.L.F., Grid 2 Sato model t=0.002s Iterations Radius [mm] 2009 ANSYS, Inc. All rights reserved. 11 ANSYS, Inc. Proprietary
12 TOPFLOW Test FZD wire-mesh sensor movable diaphragm movable diaphragm gas injection 2009 ANSYS, Inc. All rights reserved. 12 ANSYS, Inc. Proprietary
13 TOPFLOW-074 Test Case Conditions from Test Matrix Selection of test case conditions: TOPFLOW-074 test case was subject of validation in the past Superficial velocities: J G = m/s J L =1.017 m/s Wire-mesh sensor measurements at locations: z= 10, 15, 20, 40, 80, 160, 250, 520mm 2009 ANSYS, Inc. All rights reserved. 13 ANSYS, Inc. Proprietary
14 3d Bubbly Flow Around Obstacle Water Velocity Comparison Comparison CFD Experiment Absolute water velocity distribution in symmetry plane Import of exp. data into CFX-Post Pre-interpolation of exp. data to z=0.01m CFD Exp ANSYS, Inc. All rights reserved. 14 ANSYS, Inc. Proprietary
15 3d Bubbly Flow Around Obstacle Air Void Fraction Comparison Comparison CFD Experiment Air void fraction distribution in symmetry plane CFD Exp ANSYS, Inc. All rights reserved. 15 ANSYS, Inc. Proprietary
16 3d Bubbly Flow Around Obstacle Air Void Fraction Comparison 4) z=40mm 8) z=520mm 8) 7) 6) 3) z=20mm 7) z=250mm 5) 4) 3) 2) z=15mm 6) z=160mm 2) 1) 1) z=10mm 5) z=80mm 2009 ANSYS, Inc. All rights reserved. 16 ANSYS, Inc. Proprietary
17 3d Bubbly Flow Around Obstacle Cross-Sectional Air Void Fraction 5) z=80mm CFX Simulation TOPFLOW Experiment 2009 ANSYS, Inc. All rights reserved. 17 ANSYS, Inc. Proprietary
18 ANSYS CFX Experimental Data Quantitative Comparison Quantitative data cross sections z=±10, ±15, ±20, ±40, ±80, ±160, ±250, ±520mm: absolute water velocity air volume fraction z=520mm x=-35mm x=+35mm obstacle y=0mm z=-520mm 2009 ANSYS, Inc. All rights reserved. 18 ANSYS, Inc. Proprietary
19 ANSYS CFX Experimental Data Quantitative Comparison z=-80mm y=0mm Norm. Air Volume Fra action [-] Abso olute Water Ve elocity [m/s] Experiment (z=-80mm) CFX Simulation (z=-80mm) x [mm] Experiment (z=-80mm) CFX Simulation (z=-80mm) x [mm] 2009 ANSYS, Inc. All rights reserved. 19 ANSYS, Inc. Proprietary
20 ANSYS CFX Experimental Data Quantitative Comparison z=-20mm y=0mm Norm. Air Volume Fra action [-] Abso olute Water Ve elocity [m/s] Experiment (z=-20mm) CFX Simulation (z=-20mm) Experiment (z=-20mm) x [mm] CFX Simulation (z=-20mm) x [mm] 2009 ANSYS, Inc. All rights reserved. 20 ANSYS, Inc. Proprietary
21 ANSYS CFX Experimental Data Quantitative Comparison z=20mm y=0mm Norm. Air Volume Fra action [-] Abso olute Water Ve elocity [m/s] Experiment (z=20mm) CFX Simulation (z=20mm) x [mm] Experiment (z=20mm) CFX Simulation (z=20mm) x [mm] 2009 ANSYS, Inc. All rights reserved. 21 ANSYS, Inc. Proprietary
22 ANSYS CFX Experimental Data Quantitative Comparison 3.5 z=80mm y=0mm Norm. Air Volume Fra action [-] Abso olute Water Ve elocity [m/s] Experiment (z=80mm) CFX Simulation (z=80mm) x [mm] Experiment (z=80mm) CFX Simulation (z=80mm) x [mm] 2009 ANSYS, Inc. All rights reserved. 22 ANSYS, Inc. Proprietary
23 ANSYS CFX Experimental Data Quantitative Comparison z=250mm y=0mm Norm. Air Volume Fra action [-] Abso olute Water Ve elocity [m/s] Experiment (z=250mm) CFX Simulation (z=250mm) x [mm] Experiment (z=250mm) CFX Simulation (z=250mm) x [mm] 2009 ANSYS, Inc. All rights reserved. 23 ANSYS, Inc. Proprietary
24 Polydispersed Bubbly Flow Caused by Breakup & Coalescence Transition from disperse bubbly flow to slug flow: Balance between: coalescence of bubbles turbulent bubble breakup bubble size distribution; polydisperse bubbly bbl flow counter-current radial motion of small and large bubbles; more than one velocity field new population balance model (inhomogeneous MUSIG) 2009 ANSYS, Inc. All rights reserved. 24 ANSYS, Inc. Proprietary
25 Inhomogeneous MUSIG Model momentum equations are solved for N gas phases (vel. groups) size fraction equations for M i bubble size classes in each vel. group bubble coalescence and break-up over all M i MUSIG groups N(d P ) breakup/ condensation coalescence/ evaporation d d d d d d d d v 1 v 2 v 3 Velocity group mass transfer d P,krit d P Break up Coalescence 2009 ANSYS, Inc. All rights reserved. 25 ANSYS, Inc. Proprietary
26 Validation of 3x7 Inhomogeneous MUSIG Model on TOPFLOW-074 good agreement at levels A, L through R too fast spreading of the bubble plume from inlet due to too intensive turbulent dispersion fraction [-] Air volume Exp. FZR-074, level A Exp. FZR-074, level C Exp. FZR-074, level F Exp. FZR-074, level l I Exp. FZR-074, level L Exp. FZR-074, level O Exp. FZR-074, level R CFX 074-A, Inlet level (z=0.0m) CFX 074-A, level C CFX 074-A, level F CFX 074-A, level I CFX 074-A, level L CFX 074-A, level O CFX 074-A, level R x [mm] 2009 ANSYS, Inc. All rights reserved. 26 ANSYS, Inc. Proprietary
27 MUSIG Model Extension Basic population balance equations dn(m, r, t) dt Bubble number density New terms n(m,r,t) m( r,t) n(m, r, t) U(m, r, t)n(m, r,t) t r m t B D B D B B C C Size fraction equations Breakup/Coalescence terms t j ( irdf i) ( ir j duif i) SB S B D S B B S C D S C x i m m m m m m i i i i 1 for evaporation i i 1 i 1 i S i = mi m i i i i 1 i for condensation mi mi 1 mi 1 m i i i i 2009 ANSYS, Inc. All rights reserved. 27 ANSYS, Inc. Proprietary
28 TOPFLOW Test FZD 8m L~ 8 D=195mm Courtesy of FZD 2009 ANSYS, Inc. All rights reserved. 28 ANSYS, Inc. Proprietary
29 Condensation Test Case P=2 [MPa] J w =1.0 [m/s] J s =0.54 [m/s] T s =214.4 [ C] T w =210.5 [ C] T w =3.9 [K] D inj = 1 [mm] Detailed experimental data: Bubble size distribution Radial steam volume fraction distribution Dirk Lucas, Horst-Michael Prasser: Steam bubble condensation in sub-cooled water in case of co-current vertical pipe flow, Nuclear Engineering and Design, Volume 237, Issue 5, March 2007, Pages ANSYS, Inc. All rights reserved. 29 ANSYS, Inc. Proprietary
30 Physical Model Setup Standard MUSIG & Extended MUSIG 25 bubble size classes 3 velocity ygroups: 0 3 [mm],3 6 [mm], 6 30 [mm] Arranged in accordance with critical Tomiyama bubble diameter for bubble size dependent lift force Break up model: Luo & Svendsen (F B =0.025) Coalescence model: Prince & Blanch (F C =0.05) 2009 ANSYS, Inc. All rights reserved. 30 ANSYS, Inc. Proprietary
31 TOPFLOW Condensation Testcase Inlet BC Inlet Position WLF TD Force Heat Transfer Config 1 D inj = 4mm Config 2 D inj =4 mm Source Wall Source 75 mm F WLF CTD=1.5 Nu=2+0.15Re p 0.8 Pr 0.5 Config 3 D inj = 1 mm Source F mm WLF CTD=1.5 Nu=2+0.15Re 0.8 p Pr ANSYS, Inc. All rights reserved. 31 ANSYS, Inc. Proprietary
32 Results: Vapor Volume Fraction 2009 ANSYS, Inc. All Config rights reserved. 1 Config 32 2 Config 3 ANSYS, Inc. Proprietary
33 Results: Vertical Averaged Steam Distribution 2009 ANSYS, Inc. All rights reserved. 33 ANSYS, Inc. Proprietary
34 Results: Radial Steam Distribution 2009 ANSYS, Inc. All rights reserved. 34 ANSYS, Inc. Proprietary
35 Results: Radial Steam Distribution 2009 ANSYS, Inc. All rights reserved. 35 ANSYS, Inc. Proprietary
36 Results: Bubble Size Distribution 2009 ANSYS, Inc. All rights reserved. 36 ANSYS, Inc. Proprietary
37 Results: Bubble Size Distribution 2009 ANSYS, Inc. All rights reserved. 37 ANSYS, Inc. Proprietary
38 CFD Simulation for Fuel Assemblies in Nuclear Reactors Material Properties Wall Boiling & Bulk Condensation Turbulence Conjugate Heat Transfer (CHT) Multiphase Flow Modeling FSI: Stresses & Deformations Validation against Experiments 2009 ANSYS, Inc. All rights reserved. 38 ANSYS, Inc. Proprietary
39 CFD Simulation for Fuel Assemblies in Nuclear Reactors Material Properties Wall Boiling & Bulk Condensation Turbulence Conjugate Heat Transfer (CHT) Multiphase Flow Modeling FSI: Stresses & Deformations Validation against Experiments 2009 ANSYS, Inc. All rights reserved. 39 ANSYS, Inc. Proprietary
40 Multiphase Flow Regimes for Boiling Water Flow subcooled flow bubbly flow slug flow annular flow spray flow T ONB OSB wall temperature T sat mean fluid temperature subcooled boiling nucleate boiling (saturated boiling) x 2009 ANSYS, Inc. All rights reserved. 40 ANSYS, Inc. Proprietary
41 Flows with Subcooled Boiling (DNB) RPI-Wall Boiling Model Mechanistic wall heat partioning model: q Wall q F q Q q E convective heat flux q F A1 hf ( TW TL) quenching heat flux q Q A2 hq ( TW TL) evaporation heat flux q m (h h ) E G L y A 2 A1 A 2 Convective heat flux u Quenching heat flux m * * * m m t 2009 ANSYS, Inc. All rights reserved. 41 ANSYS, Inc. Proprietary
42 RPI-Wall Boiling Model Submodels for Model Closure Submodels for closure of RPI wall boiling model: Nucleation site density: Lemmert & Chawla, User Defined Bubble departure diameter: Tolubinski & Kostanchuk, Unal, Fritz, User Defined Bubble detachment frequency: Terminal rise velocity over Departure Diameter, User Defined Bubble waiting time: Proportional to Detachment Period, User Defined Quenching heat transfer: Del Valle & Kenning, User Defined Turbulent Wall Function for liquid convective heat transfer coefficient Correlation for bulk flow mean bubble diameter required: e.g. Kurul & Podowski correlation via CCL Supported combination of wall boiling & CHT in the solid GGI & 1:1 solid-fluid interfaces 2009 ANSYS, Inc. All rights reserved. 42 ANSYS, Inc. Proprietary
43 RPI Wall Boiling Model in the ANSYS CFX-Pre 12.0 GUI 2009 ANSYS, Inc. All rights reserved. 43 ANSYS, Inc. Proprietary
44 The Bartolomej et al. Testcase (1967,1982) 2009 ANSYS, Inc. All rights reserved. 44 ANSYS, Inc. Proprietary
45 The Bartolomej Test Case R = 7.7 mm Variable Value Z= 2 m q=0.5 57MW/m 2 P 4.5MPa R 7.7 mm G in 900 kg/(s m2) q q 0.57MW/m2 Subcooling 58.2 K G in =900 kg/(s m 2 ) 2009 ANSYS, Inc. All rights reserved. 45 ANSYS, Inc. Proprietary
46 Multiphase Flow Model Steam-Water 2-phase flow: Water: continuous phase Water Steam: disperse bubbles (particle model) Material properties (EOS): IAPWS-IF97 water - water steam property tables Modified law for interfacial area Kurul & Podowski type bulk bubble diameter: d B =f(t sub ) Accounting for higher volume fraction of the steam phase Turbulence Model SST turbulence model for continuous phase 0-eq. disperse phase turb. model + Sato bubble induced turbulence 2009 ANSYS, Inc. All rights reserved. 46 ANSYS, Inc. Proprietary
47 Inter-Phase Mass, Momentum and Energy Transfer Mass transfer model Thermal Phase Change Model (bulk boiling/condensation model) RPI wall boiling model Momentum transfer models Grace drag FAD turbulent dispersion force Tomiyama lift force Wall lubrication force (none, Antal, Tomiyama) Heat transfer models Water: Thermal Energy Water Steam: Saturation temperature Two resistance model Ranz Marshall correlation for bubble heat transfer 2009 ANSYS, Inc. All rights reserved. 47 ANSYS, Inc. Proprietary
48 Numerical Grids Validation on mesh hierarchy with regular refinement factor of 4 (2d meshes) Grid Grid1 Grid2 Grid3 # Nodes (uniform) 20x150 40x300 80x600 Max y Δt [s] x ANSYS, Inc. All rights reserved. 48 ANSYS, Inc. Proprietary
49 Grid ANSYS, Inc. All rights reserved. 49 ANSYS, Inc. Proprietary
50 Grid ANSYS, Inc. All rights reserved. 50 ANSYS, Inc. Proprietary
51 Grid ANSYS, Inc. All rights reserved. 51 ANSYS, Inc. Proprietary
52 Comparison to Experimental Data 2009 ANSYS, Inc. All rights reserved. 52 ANSYS, Inc. Proprietary
53 Comparison to Experimental Data - Parameter & Model Variation Influence of wall heat flux: Influence of wall lubrication force model: 2009 ANSYS, Inc. All rights reserved. 53 ANSYS, Inc. Proprietary
54 The Lee et al. Testcase (ICONE-16, 2008) 2009 ANSYS, Inc. All rights reserved. 54 ANSYS, Inc. Proprietary
55 Lee et al. (2008) Testcase Axially symmetric circular annulus Radial dimensions Inner radius of outer tube: R = mm Outer radius of inner tube: R 0 = 9.5 mm r Outlet R R0 R C Measuring Plane (for experimental and numerical Results) Core radius: R C = 3/4 R 0 Annulus width: 9.25 mm Axial dimensions Total heating section height: ht L T = 1670 mm Distance between inlet and measuring plane: L M = 1610 mm L M L T Heated Wall Adiabatic Wall Radial Position: R P Dimensionless, radial distance from inner tube (R P = 0) to outer tube (R P = 1) across the annulus: R P r R R R 0 0 Inner Tube (Heating Rod) Annulus Outer Tube 2009 ANSYS, Inc. All rights reserved. 55 ANSYS, Inc. Proprietary Axis Inlet z
56 Geometry and Mesh Geometry & Mesh generation: Figure 4: Generated one layer mesh Figure 1: 25 segment of the geometry Annulus Core Shell Figure 2: 1 simulated segment of the geometry symmetry symmetry Figure 3: 1 segment with one-layer mesh example symmetry symmetry 2009 ANSYS, Inc. All rights reserved. 56 ANSYS, Inc. Proprietary
57 Mesh Hierarchy Mesh Name Grid 01 (coarse) Grid 02 (medium) Grid 03 (fine) Domains ( 1 = HFO, 2 = CHT ) * No. of Nodes 1: : : : : : No. of Elements 1: 20x150 1: 40x300 1: 80x600 (hexahedra) 2: 40x150 2: 80x300 2: 160x600 y + max (at 1 st node near wall) Set16 ~84 ~41 ~24 Set25 ~88 ~45 ~25 Tstep Δt [s] Set Set ANSYS, Inc. All rights reserved. 57 ANSYS, Inc. Proprietary
58 Selection of Extreme/Limiting Testcase Conditions Concentrating on 2 (out of 12) datasets: Set 25 (least of all steam) Set 16 (most of all steam) Parameter comparison Set No.* q [kw m^-2] G [kg m^-2s] T in [ C] P in [kpa] ANSYS, Inc. All rights reserved. 58 ANSYS, Inc. Proprietary
59 Required Parameter Modifications in Comparison to PWR Conditions Found that submodels need modifications for BWR conditions (see also Tu&Yeoh, Anglart et al., Krepper, Koncar): 1. Bulk bubble diameter (BBD) Kurul & Podowski d B,max wall modified d B law d B,max 2. Bubble departure diameter (BDD) Tolubinski & Kostanchuk d W ~0.5mm max. const. bubble dept. diam. d W =1mm - 3mm 3. A 2 - Wall area fraction influenced by steam bubbles default increased up to ANSYS, Inc. All rights reserved. 59 ANSYS, Inc. Proprietary
60 BBD & BDD Modifications Test Matrix Overview Trying to systematically increase Bubble Departure Diameter to investigate its influence on Heat Flux to Vapor (Q V ) profile Test series with increasing BDD starting from d W.max 0.5 mm 1 mm; 2 mm; 3 mm T&K * 4.0 BDD Tolubinsky & Kostanchuk BDD User defined d W [mm] K&P yes - bbdmod01-1 = const. bbdmod02-2 = const. bbdmod03-3 = const ANSYS, Inc. All rights reserved. 60 ANSYS, Inc. Proprietary
61 BBD Modification / Set 25: Gas Volume z = 1610 [mm] Set25 : Bulk Diameter Modification Comparison: Gas Volume Fraction (r G ) r G [ ] Radial Position (R p ) [ ] G3_K&P G3_dbmod01 G3_dbmod02 G3_dbmod03 Experimental Data 2009 ANSYS, Inc. All rights reserved. 61 ANSYS, Inc. Proprietary
62 BDD Modification / Set 25: Gas Volume z = 1610 [mm] Set25 Bubble Departure Diameter Modification Comparison: Gas Volume Fraction (r G ) r G [ ] Radial Position (R p ) [ ] G3_K&P G3_dbmod02_bddmod01 bddmod01 G3_dbmod02_bddmod02 bddmod02 G3_dbmod02_bddmod03 Experimental Data 2009 ANSYS, Inc. All rights reserved. 62 ANSYS, Inc. Proprietary
63 A 2F Limiter Modification: Results Set 25, Gas Volume z=1610[mm] rg [ ] 0,45 0, ,35 0,30 0,25 0, ,15 0,10 0,05 0,00 Set25 A 2F Mod Comparison: Gas Volume Fraction (r G ) ,1 02 0,2 03 0,3 04 0,4 05 0,5 06 0,6 07 0,7 08 0,8 09 0,9 1 G3_K&P G3_dbmod02_bddmod02_A2F02 Experimental Data Radial Position (R p ) [ ] G3_dbmod02_bddmod01_A2F02 G3_dbmod02_bddmod03_A2F ANSYS, Inc. All rights reserved. 63 ANSYS, Inc. Proprietary
64 Grid Independency: Results Set 25, Gas Volume z = 1610 [mm] Set25 New Grid Comparison: Gas Volume Fraction (r G ) rg [ ] 0,40 0, ,30 0,25 0,20 0,15 0,10 0,05 0,00 0 0,1 0,2 0,3 0,4 0,5 0,6 0,7 0,8 0,9 1 Radial Position (R p ) [ ] G1_dbmod02_bddmod02_A2F02 G3_dbmod02_bddmod02_A2F02 Experimental Data G2_dbmod02_bddmod02_A2F02 G4_dbmod02_bddmod02_A2F ANSYS, Inc. All rights reserved. 64 ANSYS, Inc. Proprietary
65 The Lee et al. Testcase (ICONE-16, 2008) - Conjugate Heat Transfer ANSYS, Inc. All rights reserved. 65 ANSYS, Inc. Proprietary
66 Heat Source in Solid Material & Conjugate Heat Transfer Prediction HFO (Heat Flux Only): Fluid Domain (Annulus) area specific heat flux boundary condition # Outlet Fluid Domain Inlet CHT (Conjugated Heat Transfer): Fluid Domain (Annulus) + Solid Domain (Non-Heated Rod Shell) + + Solid Domain (Heated Rod Core) volume specific heat source # Outlet Solid Domain # Solid Domain Fluid Domain Inlet 2009 ANSYS, Inc. All rights reserved. 66 ANSYS, Inc. Proprietary
67 The RPI Wall Boiling Model: Lee et al. Testcase with CHT Specific energy source in solid material, Set25 (equiv. to q Wall ): E Core = [W/m 3 ] Temperature and Steam VF distribution in vertical plane 2009 ANSYS, Inc. All rights reserved. 67 ANSYS, Inc. Proprietary
68 The RPI Wall Boiling Model: Lee et al. Testcase with CHT Set25 & CHT: Water temperature monitors x W =1.5mm, z=83.5mm, T L z=835mm T L Outlet Iterations T L Intlet Iterations 2009 ANSYS, Inc. All rights reserved. 68 ANSYS, Inc. Proprietary
69 The RPI Wall Boiling Model: Lee et al. Testcase with CHT Set25 & CHT: Grid independence for temperature z=1610[mm] Heated Core Fluid Domain Unheated Cladding 2009 ANSYS, Inc. All rights reserved. 69 ANSYS, Inc. Proprietary
70 The RPI Wall Boiling Model: Lee et al. Testcase with CHT Set25 & CHT: Vapour VF z=1610[mm] 2009 ANSYS, Inc. All rights reserved. 70 ANSYS, Inc. Proprietary
71 New R&D Consortium R&D Initiative: Modeling, Simulation & Experiments for Boiling Processes in Fuel Assemblies of PWR Karlsruhe Inst. of Technology (KIT) ANSYS Germany TUD, Dept. Fluid Mechanics FZ Dresden/ Rossendorf TUM, Dept. Thermodynamics TUD, Dept. Nucl. Eng. Univ. Bochum, Dept. Energy Systems Univ. Appl. Sciences Zittau/ Görlitz TUD Medical Faculty 2009 ANSYS, Inc. All rights reserved. 71 ANSYS, Inc. Proprietary
72 Modeling, Simulation & Experiments for Boiling Processes in Fuel Assemblies of PWR Ultrafast electron beam X-ray CT of fuel rod bundle in titanium pipe on FZD: Images by courtesy of U. Hampel, FZD 2009 ANSYS, Inc. All rights reserved. 72 ANSYS, Inc. Proprietary
73 Modeling, Simulation & Experiments for Boiling Processes in Fuel Assemblies of PWR Wall boiling simulation in a 3x3 rod bundle with spacer grid: Wall superheat T W -T Sat 2009 ANSYS, Inc. All rights reserved. 73 ANSYS, Inc. Proprietary
74 Summary & Outlook Overview on ANSYS CFD multiphase flow model development and validation Continuous effort in model improvement, R&D Emphasis in validation on BPG, comparison to data, geometry & grid independent modeling High interoperability of physical models Outlook: Ongoing & customer driven CFD model development Research cooperation with Industry & Academia More & more complex MPF phenomena Coupling of wall boiling model to inhomogeneous MUSIG Extension of the wall heat partitioning in wall boiling model 2009 ANSYS, Inc. All rights reserved. 74 ANSYS, Inc. Proprietary
75 Thank You! 2009 ANSYS, Inc. All rights reserved. 75 ANSYS, Inc. Proprietary
Development and Validation of the Wall Boiling Model in ANSYS CFD
Development and Validation of the Wall Boiling Model in ANSYS CFD Th. Frank, C. Lifante, A.D. Burns PBU, Funded CFD Development ANSYS Germany Thomas.Frank@ansys.com E. Krepper, R. Rzehak FZ Dresden-Rossendorf
More informationCFD-Modeling of Boiling Processes
CFD-Modeling of Boiling Processes 1 C. Lifante 1, T. Frank 1, A. Burns 2, E. Krepper 3, R. Rzehak 3 conxita.lifante@ansys.com 1 ANSYS Germany, 2 ANSYS UK, 3 HZDR Outline Introduction Motivation Mathematical
More informationINVESTIGATION OF THE PWR SUBCHANNEL VOID DISTRIBUTION BENCHMARK (OECD/NRC PSBT BENCHMARK) USING ANSYS CFX
INVESTIGATION OF THE PWR SUBCHANNEL VOID DISTRIBUTION BENCHMARK (OECD/NRC PSBT BENCHMARK) USING ANSYS CFX Th. Frank 1, F. Reiterer 1 and C. Lifante 1 1 ANSYS Germany GmbH, Otterfing, Germany Thomas.Frank@ansys.com,
More informationModeling of Wall-boiling Phenomena from Nucleate Subcooled Boiling up to CHF Conditions
Modeling of Wall-boiling Phenomena from Nucleate Subcooled Boiling up to CHF Conditions Thomas Frank (1), Amine Ben Hadj Ali (1), Conxita Lifante (1), Florian Kaiser (2), Stephan Gabriel (2), Henning Eickenbusch
More informationMultiphase Flow Modeling & Simulation with Application to Water-Vapor Flows Through Fuel Rod Bundles of Nuclear Reactors
Multiphase Flow Modeling & Simulation with Application to Water-Vapor Flows Through Fuel Rod Bundles of Nuclear Reactors Thomas Frank ANSYS Germany, Otterfing Thomas.Frank@ansys.com 2006 ANSYS, Inc. Th.
More informationPrediction of Convective Boiling up to Critical Heat Flux (CHF) Conditions for Test Facilities with Vertical Heaters
Prediction of Convective Boiling up to Critical Heat Flux (CHF) Conditions for Test Facilities with Vertical Heaters Thomas Frank (1), Amine Ben Hadj Ali (1), Conxita Lifante (1), Moritz Bruder (2), Florian
More informationCFD-Modelling of subcooled boiling and Applications in the Nuclear Technology
CFD-Modelling of subcooled boiling and Applications in the Nuclear Technology Eckhard Krepper Jahrestagung Kerntechnik 2011 Fachsitzung: CFD-Simulationen zu sicherheitsrelevanten Fragestellungen Text optional:
More informationDEVELOPMENT OF A MULTIPLE VELOCITY MULTIPLE SIZE GROUP MODEL FOR POLY-DISPERSED MULTIPHASE FLOWS
DEVELOPMENT OF A MULTIPLE VELOCITY MULTIPLE SIZE GROUP MODEL FOR POLY-DISPERSED MULTIPHASE FLOWS Jun-Mei Shi, Phil Zwart 1, Thomas Frank 2, Ulrich Rohde, and Horst-Michael Prasser 1. Introduction Poly-dispersed
More informationCFD Simulation of Sodium Boiling in Heated Pipe using RPI Model
Proceedings of the 2 nd World Congress on Momentum, Heat and Mass Transfer (MHMT 17) Barcelona, Spain April 6 8, 2017 Paper No. ICMFHT 114 ISSN: 2371-5316 DOI: 10.11159/icmfht17.114 CFD Simulation of Sodium
More informationTurbulence Dispersion Force Physics, Model Derivation and Evaluation
Turbulence Dispersion Force Physics, Model Derivation and Evaluation J.-M. Shi, T. Frank, A. Burns 3 Institute of Safety Research, FZ Rossendorf shi@fz-rossendorf.de ANSYS CFX Germany 3 ANSYS CFX FZR ANSYS
More informationEulerian model for the prediction of nucleate boiling of refrigerant in heat exchangers
Advanced Computational Methods and Experiments in Heat Transfer XI 51 Eulerian model for the prediction of nucleate boiling of refrigerant in heat exchangers D. Simón, M. C. Paz, A. Eirís&E.Suárez E.T.S.
More informationResearch Article CFD Modeling of Boiling Flow in PSBT 5 5Bundle
Science and Technology of Nuclear Installations Volume 2012, Article ID 795935, 8 pages doi:10.1155/2012/795935 Research Article CFD Modeling of Boiling Flow in PSBT 5 5Bundle Simon Lo and Joseph Osman
More informationDEVELOPMENT OF COMPUTATIONAL MULTIFLUID DYNAMICS MODELS FOR NUCLEAR REACTOR APPLICATIONS
DEVELOPMENT OF COMPUTATIONAL MULTIFLUID DYNAMICS MODELS FOR NUCLEAR REACTOR APPLICATIONS Henry Anglart Royal Institute of Technology, Department of Physics Division of Nuclear Reactor Technology Stocholm,
More informationCFD SIMULATION OF THE DEPARTURE FROM NUCLEATE BOILING
CFD SIMULATION OF THE DEPARTURE FROM NUCLEATE BOILING Ladislav Vyskocil and Jiri Macek UJV Rez a. s., Dept. of Safety Analyses, Hlavni 130, 250 68 Husinec Rez, Czech Republic Ladislav.Vyskocil@ujv.cz;
More informationAPPLICATION OF RPI MODEL: PREDICTION OF SUBCOOLED BOILING AND DNB IN VERTICAL PIPES
APPLICATION OF RPI MODEL: PREDICTION OF SUBCOOLED BOILING AND DNB IN VERTICAL PIPES Rui Zhang, Wenwen Zhang, Tenglong Cong, Wenxi Tian, G H Su, Suizheng Qiu School of Nuclear Science and Technology, Xi
More informationUSE OF CFD TO PREDICT CRITICAL HEAT FLUX IN ROD BUNDLES
USE OF CFD TO PREDICT CRITICAL HEAT FLUX IN ROD BUNDLES Z. E. Karoutas, Y. Xu, L. David Smith, I, P. F. Joffre, Y. Sung Westinghouse Electric Company 5801 Bluff Rd, Hopkins, SC 29061 karoutze@westinghouse.com;
More informationVALIDATION OF CFD-BWR, A NEW TWO-PHASE COMPUTATIONAL FLUID DYNAMICS MODEL FOR BOILING WATER REACTOR ANALYSIS
VALIDATION OF CFD-BWR, A NEW TWO-PHASE COMPUTATIONAL FLUID DYNAMICS MODEL FOR BOILING WATER REACTOR ANALYSIS V.Ustineno 1, M.Samigulin 1, A.Ioilev 1, S.Lo 2, A.Tentner 3, A.Lychagin 4, A.Razin 4, V.Girin
More informationMultiphase Flows. Mohammed Azhar Phil Stopford
Multiphase Flows Mohammed Azhar Phil Stopford 1 Outline VOF Model VOF Coupled Solver Free surface flow applications Eulerian Model DQMOM Boiling Model enhancements Multi-fluid flow applications Coupled
More informationANALYSIS AND APPLICATIONS OF A TWO-FLUID MULTI-FIELD HYDRODYNAMIC MODEL FOR CHURN-TURBULENT FLOWS
Proceedings of the 2013 21st International Conference on Nuclear Engineering ICONE21 July 29 - August 2, 2013, Chengdu, China ICONE21-16297 ANALYSIS AND APPLICATIONS OF A TWO-FLUID MULTI-FIELD HYDRODYNAMIC
More informationLaboratory of Thermal Hydraulics. General Overview
Visit of Nuclear Master Students Laboratory of Thermal Hydraulics General Overview Horst-Michael Prasser December 04, 2009 Paul Scherrer Institut Main Goals Development of analytical and experimental methods
More informationInvestigation of Three-Dimensional Upward and Downward Directed Gas-Liquid Two-Phase Bubbly Flows in a 180 o -Bent Tube
Investigation of Three-Dimensional Upward and Downward Directed Gas-Liquid Two-Phase Bubbly Flows in a 180 o -Bent Tube Th. Frank, R. Lechner, F. Menter CFX Development, ANSYS Germany GmbH, Staudenfeldweg
More informationNumerical Investigation of Nucleate Boiling Flow in Water Based Bubble Bumps
International Journal of Fluid Mechanics & Thermal Sciences 2015; 1(2): 36-41 Published online June 15, 2015 (http://www.sciencepublishinggroup.com/j/ijfmts) doi: 10.11648/j.ijfmts.20150102.14 Numerical
More informationCFD modelling of multiphase flows
1 Lecture CFD-3 CFD modelling of multiphase flows Simon Lo CD-adapco Trident House, Basil Hill Road Didcot, OX11 7HJ, UK simon.lo@cd-adapco.com 2 VOF Free surface flows LMP Droplet flows Liquid film DEM
More informationMulti-phase mixture modelling of nucleate boiling applied to engine coolant flows
Computational Methods in Multiphase Flow V 135 Multi-phase mixture modelling of nucleate boiling applied to engine coolant flows V. Pržulj & M. Shala Ricardo Software, Ricardo UK Limited Shoreham-by-Sea,
More informationEuler-Euler Modeling of Mass-Transfer in Bubbly Flows
Euler-Euler Modeling of Mass-Transfer in Bubbly Flows Roland Rzehak Eckhard Krepper Text optional: Institutsname Prof. Dr. Hans Mustermann www.fzd.de Mitglied der Leibniz-Gemeinschaft Overview Motivation
More informationDevelopment of a Validation and Uncertainty Quantification Framework for Closure Models in Multiphase CFD Solver
Development of a Validation and Uncertainty Quantification Framework for Closure Models in Multiphase CFD Solver Yang Liu and Nam Dinh Multi-Physics Model Validation Workshop June/28/2017 1 Multiphase
More informationModelling of Gas-Liquid Two-Phase Flows in Vertical Pipes using PHOENICS
Modelling of Gas-Liquid Two-Phase Flows in Vertical Pipes using PHOENICS Vladimir Agranat, Masahiro Kawaji, Albert M.C. Chan* Department of Chemical Engineering and Applied Chemistry University of Toronto,
More informationCFD-Modeling of Turbulent Flows in a 3x3 Rod Bundle and Comparison to Experiments
CFD-Modeling of Turbulent Flows in a 3x3 Rod Bundle and Comparison to Experiments C. Lifante 1, B. Krull 1, Th. Frank 1, R. Franz 2, U. Hampel 2 1 PBU, ANSYS Germany, Otterfing 2 Institute of Safety Research,
More informationSubgrid Scale Modeling and the art of CFD
NSE Nuclear Science & Engineering at MIT science : systems : society Subgrid Scale Modeling and the art of CFD Massachusetts Institute of Technology Emilio Baglietto, NSE Multiphase-CFD: a full-scope redesign
More informationThis is a repository copy of CFD Simulation of Boiling Flows with an Eulerian-Eulerian Two-Fluid Model.
This is a repository copy of CFD Simulation of Boiling Flows with an Eulerian-Eulerian Two-Fluid Model. White Rose Research Online URL for this paper: http://eprints.whiterose.ac.uk/128021/ Version: Accepted
More informationTHERMAL HYDRAULIC REACTOR CORE CALCULATIONS BASED ON COUPLING THE CFD CODE ANSYS CFX WITH THE 3D NEUTRON KINETIC CORE MODEL DYN3D
THERMAL HYDRAULIC REACTOR CORE CALCULATIONS BASED ON COUPLING THE CFD CODE ANSYS CFX WITH THE 3D NEUTRON KINETIC CORE MODEL DYN3D A. Grahn, S. Kliem, U. Rohde Forschungszentrum Dresden-Rossendorf, Institute
More informationWP2.3: Boiling Water Reactor Thermal- Hydraulics
WP2.3: Boiling Water Reactor Thermal- Hydraulics H. Anglart, D. Caraghiaur, D. Lakehal, J. Pérez, V. Tanskanen, M. Ilvonen BWR Thermal-hydraulic issues CFD Eulerian/Eulerian approach (KTH) Annular flow
More informationNumerical Analysis of Critical Heat Flux Phenomenon in a Nuclear Power Plant Core Channel in the Presence of Mixing Vanes
AUT Journal of Mechanical Engineering AUT J. Mech. Eng., 1(2) (2017) 119-130 DOI: 10.22060/mej.2017.12928.5472 Numerical Analysis of Critical Heat Flux Phenomenon in a Nuclear Power Plant Core Channel
More informationMODELLING, SIMULATION AND EXPERIMENTS ON BOILING PROCESSES IN PRESSURIZED WATER REACTORS ABSTRACT
MODELLING, SIMULATION AND EXPERIMENTS ON BOILING PROCESSES IN PRESSURIZED WATER REACTORS E. Krepper 1, R. Rzehak 1, U. Hampel 1, R. Hampel 2, C. Schneider 2, Th. Frank 3, J. Fröhlich 4, A. Hurtado 4, E.
More informationMultiphase Flow and Heat Transfer
Multiphase Flow and Heat Transfer ME546 -Sudheer Siddapureddy sudheer@iitp.ac.in Two Phase Flow Reference: S. Mostafa Ghiaasiaan, Two-Phase Flow, Boiling and Condensation, Cambridge University Press. http://dx.doi.org/10.1017/cbo9780511619410
More informationChapter 10: Boiling and Condensation 1. Based on lecture by Yoav Peles, Mech. Aero. Nuc. Eng., RPI.
Chapter 10: Boiling and Condensation 1 1 Based on lecture by Yoav Peles, Mech. Aero. Nuc. Eng., RPI. Objectives When you finish studying this chapter, you should be able to: Differentiate between evaporation
More informationInvestigation of CTF void fraction prediction by ENTEK BM experiment data
Investigation of CTF void fraction prediction by ENTEK BM experiment data Abstract Hoang Minh Giang 1, Hoang Tan Hung 1, Nguyen Phu Khanh 2 1 Nuclear Safety Center, Institute for Nuclear Science and Technology
More informationheat transfer process where a liquid undergoes a phase change into a vapor (gas)
Two-Phase: Overview Two-Phase two-phase heat transfer describes phenomena where a change of phase (liquid/gas) occurs during and/or due to the heat transfer process two-phase heat transfer generally considers
More informationUrea Injection and Preparation in Diesel Applications Multiphase Multicomponent Modeling using Star-CD
, London Urea Injection and Preparation in Diesel Applications Multiphase Multicomponent Modeling using Star-CD Institute for Powertrains & Automotive Technology Dipl.-Phys. Simon Fischer Dr. Thomas Lauer
More informationMECHANISTIC MODELING OF TWO-PHASE FLOW AROUND SPACER GRIDS WITH MIXING VANES
MECHANISTIC MODELING OF TWO-PHASE FLOW AROUND SPACER GRIDS WITH MIXING VANES B. M. Waite, D. R. Shaver and M. Z. Podowski Department of Mechanical, Aerospace and Nuclear Engineering, Rensselaer Polytechnic
More informationModelling of phase change for Two-Phase Refrigerant Flow inside Capillary Tube under Adiabatic Conditions
International Journal of Current Engineering and Technology E-ISSN 2277 4106, P-ISSN 2347 5161 2016 INPRESSCO, All Rights Reserved Available at http://inpressco.com/category/ijcet Research Article Modelling
More informationLectures on Applied Reactor Technology and Nuclear Power Safety. Lecture No 6
Lectures on Nuclear Power Safety Lecture No 6 Title: Introduction to Thermal-Hydraulic Analysis of Nuclear Reactor Cores Department of Energy Technology KTH Spring 2005 Slide No 1 Outline of the Lecture
More informationDevelopment of twophaseeulerfoam
ISPRAS OPEN 2016 NUMERICAL STUDY OF SADDLE-SHAPED VOID FRACTION PROFILES EFFECT ON THERMAL HYDRAULIC PARAMETERS OF THE CHANNEL WITH TWO-PHASE FLOW USING OPENFOAM AND COMPARISON WITH EXPERIMENTS Varseev
More informationHeat Transfer Modeling using ANSYS FLUENT
Lecture 1 - Introduction 14.5 Release Heat Transfer Modeling using ANSYS FLUENT 2013 ANSYS, Inc. March 28, 2013 1 Release 14.5 Outline Modes of Heat Transfer Basic Heat Transfer Phenomena Conduction Convection
More informationNUMERICAL SIMULATION OF SLUG FLOW REGIME FOR AN AIR-WATER TWO-PHASE FLOW IN HORIZONTAL PIPES
The 11 th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-11) Paper: 038 NUMERICAL SIMULATION OF SLUG FLOW REGIME FOR AN AIR-WATER TWO-PHASE FLOW IN HORIZONTAL PIPES Thomas
More informationAnalysis and interpretation of the LIVE-L6 experiment
Analysis and interpretation of the LIVE-L6 experiment A. Palagin, A. Miassoedov, X. Gaus-Liu (KIT), M. Buck (IKE), C.T. Tran, P. Kudinov (KTH), L. Carenini (IRSN), C. Koellein, W. Luther (GRS) V. Chudanov
More informationA Validation and Uncertainty Quantification Framework for. Eulerian-Eulerian Two-Fluid Model based Multiphase-CFD Solver. Part I: Methodology
A Validation and Uncertainty Quantification Framework for Eulerian-Eulerian Two-Fluid Model based Multiphase-CFD Solver. Part I: Methodology Yang Liu 1,*, Nam Dinh 1, Ralph Smith 2 1 Department of Nuclear
More informationFluid Flow, Heat Transfer and Boiling in Micro-Channels
L.P. Yarin A. Mosyak G. Hetsroni Fluid Flow, Heat Transfer and Boiling in Micro-Channels 4Q Springer 1 Introduction 1 1.1 General Overview 1 1.2 Scope and Contents of Part 1 2 1.3 Scope and Contents of
More informationCFD SIMULATIONS OF SINGLE AND TWO-PHASE MIXING PROESSES IN STIRRED TANK REACTORS
CFD SIMULATIONS OF SINGLE AND TWO-PHASE MIXING PROESSES IN STIRRED TANK REACTORS Hristo Vesselinov Hristov, Stephan Boden, Günther Hessel, Holger Kryk, Horst-Michael Prasser, and Wilfried Schmitt. Introduction
More informationENGINEERING OF NUCLEAR REACTORS
22.312 ENGINEERING OF NUCLEAR REACTORS Monday, December 17 th, 2007, 9:00am-12:00 pm FINAL EXAM SOLUTIONS Problem 1 (45%) Analysis of Decay Heat Removal during a Severe Accident i) The energy balance for
More informationAxial profiles of heat transfer coefficients in a liquid film evaporator
Axial profiles of heat transfer coefficients in a liquid film evaporator Pavel Timár, Ján Stopka, Vladimír Báleš Department of Chemical and Biochemical Engineering, Faculty of Chemical and Food Technology,
More informationNEAR-WALL TURBULENCE-BUBBLES INTERACTIONS IN A CHANNEL FLOW AT Re =400: A DNS/LES INVESTIGATION
ABSTRACT NEAR-WALL TURBULENCE-BUBBLES INTERACTIONS IN A CHANNEL FLOW AT Re =400: A DNS/LES INVESTIGATION D. Métrailler, S. Reboux and D. Lakehal ASCOMP GmbH Zurich, Technoparkstr. 1, Switzerland Metrailler@ascomp.ch;
More informationEffect of Standoff Distance on the Partitioning of Surface Heat Flux during Subcooled Jet Impingement Boiling
Effect of Standoff Distance on the Partitioning of Surface Heat Flux during Subcooled Jet Impingement Boiling S. Abishek, R. Narayanaswamy, V. Narayanan Department of Mechanical Engineering, Curtin University,
More informationHeat Transfer with Phase Change
CM3110 Transport I Part II: Heat Transfer Heat Transfer with Phase Change Evaporators and Condensers Professor Faith Morrison Department of Chemical Engineering Michigan Technological University 1 Heat
More informationApplication of System Codes to Void Fraction Prediction in Heated Vertical Subchannels
Application of System Codes to Void Fraction Prediction in Heated Vertical Subchannels Taewan Kim Incheon National University, 119 Academy-ro, Yeonsu-gu, Incheon 22012, Republic of Korea. Orcid: 0000-0001-9449-7502
More informationCOMPUTATIONAL MULTI-FLUID DYNAMICS PREDICTIONS OF DNB
COMPUTATIONAL MULTI-FLUID DYNAMICS PREDICTIONS OF DNB ABSTRACT S. Mimouni Electricité de France, R&D Division, 6 Quai Watier 78401 Chatou, France stephane.mimouni@edf.fr Extensive efforts have been made
More informationDevelopments and Applications of TRACE/CFD Model of. Maanshan PWR Pressure Vessel
Developments and Applications of TRACE/CFD Model of Maanshan PWR Pressure Vessel Yu-Ting Ku 1, Yung-Shin Tseng 1, Jung-Hua Yang 1 Shao-Wen Chen 2, Jong-Rong Wang 2,3, and Chunkuan Shin 2,3 1 : Department
More informationNumerical Simulation of Gas-Liquid-Reactors with Bubbly Flows using a Hybrid Multiphase-CFD Approach
Numerical Simulation of Gas-Liquid-Reactors with Bubbly Flows using a Hybrid Multiphase-CFD Approach TFM Hybrid Interface Resolving Two-Fluid Model (HIRES-TFM) by Coupling of the Volume-of-Fluid (VOF)
More informationVALIDATION OF CFD-MODELS FOR NATURAL CONVECTION, HEAT TRANSFER AND TURBULENCE PHENOMENA. J. Stewering, B. Schramm, M. Sonnenkalb
VALIDATION OF CFD-MODELS FOR NATURAL CONVECTION, HEAT TRANSFER AND TURBULENCE PHENOMENA J. Stewering, B. Schramm, M. Sonnenkalb Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbh, Schwertnergasse
More informationSimplified Model of WWER-440 Fuel Assembly for ThermoHydraulic Analysis
1 Portál pre odborné publikovanie ISSN 1338-0087 Simplified Model of WWER-440 Fuel Assembly for ThermoHydraulic Analysis Jakubec Jakub Elektrotechnika 13.02.2013 This work deals with thermo-hydraulic processes
More information3D CFD and FEM Evaluations of RPV Stress Intensity Factor during PTS Loading
E-Journal of Advanced Maintenance Vol.9-2 (2017) 84-90 Japan Society of Maintenology 3D CFD and FEM Evaluations of RPV Stress Intensity Factor during PTS Loading Xiaoyong Ruan 1,*, Toshiki Nakasuji 1 and
More informationJournal of NUCLEAR SCIENCE and TECHNOLOGY, Vol. 41, No. 7, p (July 2004)
Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol. 41, No. 7, p. 765 770 (July 2004) TECHNICAL REPORT Experimental and Operational Verification of the HTR-10 Once-Through Steam Generator (SG) Heat-transfer
More informationCFD MODELLING AND VALIDATION OF WALL CONDENSATION IN THE PRESENCE OF NON-CONDENSABLE GASES
CFD MODELLING AND VALIDATION OF WALL CONDENSATION IN THE PRESENCE OF NON-CONDENSABLE GASES G. Zschaeck *, T. Frank * and A. D. Burns * ANSYS Germany GmbH, Staudenfeldweg 12, Otterfing, 83624, Germany ANSYS
More informationDevelopment of a one-dimensional boiling model: Part I A two-phase flow pattern map for a heavy hydrocarbon feedstock
Development of a one-dimensional boiling model: Part I A two-phase flow pattern map for a heavy hydrocarbon feedstock Pieter Verhees, Abdul Akhras Rahman, Kevin M. Van Geem, Geraldine J. Heynderickx Laboratory
More informationWP2.1: Pressurized Thermal Shock
WP2.1: Pressurized Thermal Shock D. Lucas, P. Apanasevich, B. Niceno, C. Heib, P. Coste, M. Boucker, C. Raynauld, J. Lakehal, I. Tiselj, M. Scheuerer, D. Bestion Work package 2.1: Pressurized Thermal Shock
More informationIHTC DRAFT MEASUREMENT OF LIQUID FILM THICKNESS IN MICRO TUBE ANNULAR FLOW
DRAFT Proceedings of the 14 th International Heat Transfer Conference IHTC14 August 8-13, 2010, Washington D.C., USA IHTC14-23176 MEASUREMENT OF LIQUID FILM THICKNESS IN MICRO TUBE ANNULAR FLOW Hiroshi
More informationHeat Transfer of Condensation in Smooth Round Tube from Superheated Vapor
Purdue University Purdue e-pubs International Refrigeration and Air Conditioning Conference School of Mechanical Engineering 2016 Heat Transfer of Condensation in Smooth Round Tube from Superheated Vapor
More informationCOMPARISON OF COBRA-TF AND VIPRE-01 AGAINST LOW FLOW CODE ASSESSMENT PROBLEMS.
COMPARISON OF COBRA-TF AND VIPRE-01 AGAINST LOW FLOW CODE ASSESSMENT PROBLEMS A. Galimov a, M. Bradbury b, G. Gose c, R. Salko d, C. Delfino a a NuScale Power LLC, 1100 Circle Blvd., Suite 200, Corvallis,
More informationDepartment of Engineering and System Science, National Tsing Hua University,
3rd International Conference on Materials Engineering, Manufacturing Technology and Control (ICMEMTC 2016) The Establishment and Application of TRACE/CFD Model for Maanshan PWR Nuclear Power Plant Yu-Ting
More informationModelling multiphase flows in the Chemical and Process Industry
Modelling multiphase flows in the Chemical and Process Industry Simon Lo 9/11/09 Contents Breakup and coalescence in bubbly flows Particle flows with the Discrete Element Modelling approach Multiphase
More informationTutorial 1. Where Nu=(hl/k); Reynolds number Re=(Vlρ/µ) and Prandtl number Pr=(µCp/k)
Tutorial 1 1. Explain in detail the mechanism of forced convection. Show by dimensional analysis (Rayleigh method) that data for forced convection may be correlated by an equation of the form Nu = φ (Re,
More informationIHMTC EULER-EULER TWO-FLUID MODEL BASED CODE DEVELOPMENT FOR TWO-PHASE FLOW SYSTEMS
Proceedings of the 24th National and 2nd International ISHMT-ASTFE Heat and Mass Transfer Conference (IHMTC-2017), December 27-30, 2017, BITS-Pilani, Hyderabad, India IHMTC2017-13-0160 EULER-EULER TWO-FLUID
More informationHYDRODYNAMIC MODELING OF MINERAL WOOL FIBER SUSPENSIONS IN A TWO-DIMENSIONAL FLOW
HYDRODYNAMIC MODELING OF MINERAL WOOL FIBER SUSPENSIONS IN A TWO-DIMENSIONAL FLOW Gregory M. Cartland Glover, Alexander Grahn, Eckhard Krepper, Frank-Peter Weiss Forschungszentrum Dresden-Rossendorf Institut
More informationDetailed Modeling of Passive Auto-Catalytic Recombiner Operational Behavior with the Coupled REKODIREKT-CFX Approach
Mitglied der Helmholtz-Gemeinschaft Detailed Modeling of Passive Auto-Catalytic Recombiner Operational Behavior with the Coupled REKODIREKT-CFX Approach S. Kelm, E.-A.Reinecke, *Hans-Josef Allelein *Institute
More informationRESEARCH OF THE BUNDLE CHF PREDICTION BASED ON THE MINIMUM DNBR POINT AND THE BO POINT METHODS
RESEARCH OF THE BUNDLE CHF PREDICTION BASED ON THE MINIMUM DNBR POINT AND THE BO POINT METHODS Wei Liu 1, Jianqiang Shan 2 1 :Science and Technology on Reactor System Design Technology Laboratory, Nuclear
More informationCFX SIMULATION OF A HORIZONTAL HEATER RODS TEST
CFX SIMULATION OF A HORIZONTAL HEATER RODS TEST Hyoung Tae Kim, Bo Wook Rhee, Joo Hwan Park Korea Atomic Energy Research Institute 150 Dukjin-Dong, Yusong-Gu, Daejon 305-353, Korea kht@kaeri.re.kr Abstract
More informationNumerical Study of Hydrodynamics in an External-Loop Air-Lift Reactor
Numerical Study of Hydrodynamics in an External-Loop Air-Lift Reactor Joanna Karcz *, Marcelina Bitenc, Marek Domański, Łukasz Kacperski West Pomeranian University of Technology, Szczecin, Dept. of Chem.
More information2017 Water Reactor Fuel Performance Meeting September 10 (Sun) ~ 14 (Thu), 2017 Ramada Plaza Jeju Jeju Island, Korea
ACE/ATRIUM 11 Mechanistic Critical Power Correlation for AREVA NP s Advanced Fuel Assembly Design K. Greene 1, J. Kronenberg 2, R. Graebert 2 1 Affiliation Information: 2101 Horn Rapids Road, Richland,
More informationAn experimental investigation on condensation of R134a refrigerant in microchannel heat exchanger
Journal of Physics: Conference Series PAPER OPEN ACCESS An eperimental investigation on condensation of R134a refrigerant in microchannel heat echanger To cite this article: A S Shamirzaev 218 J. Phys.:
More informationEFFECT OF DISTRIBUTION OF VOLUMETRIC HEAT GENERATION ON MODERATOR TEMPERATURE DISTRIBUTION
EFFECT OF DISTRIBUTION OF VOLUMETRIC HEAT GENERATION ON MODERATOR TEMPERATURE DISTRIBUTION A. K. Kansal, P. Suryanarayana, N. K. Maheshwari Reactor Engineering Division, Bhabha Atomic Research Centre,
More informationHEAT TRANSFER CAPABILITY OF A THERMOSYPHON HEAT TRANSPORT DEVICE WITH EXPERIMENTAL AND CFD STUDIES
HEAT TRANSFER CAPABILITY OF A THERMOSYPHON HEAT TRANSPORT DEVICE WITH EXPERIMENTAL AND CFD STUDIES B.M. Lingade a*, Elizabeth Raju b, A Borgohain a, N.K. Maheshwari a, P.K.Vijayan a a Reactor Engineering
More informationA PWR HOT-ROD MODEL: RELAP5/MOD3.2.2Y AS A SUBCHANNEL CODE I.C. KIRSTEN (1), G.R. KIMBER (2), R. PAGE (3), J.R. JONES (1) ABSTRACT
FR0200515 9 lh International Conference on Nuclear Engineering, ICONE-9 8-12 April 2001, Nice, France A PWR HOT-ROD MODEL: RELAP5/MOD3.2.2Y AS A SUBCHANNEL CODE I.C. KIRSTEN (1), G.R. KIMBER (2), R. PAGE
More informationVERIFICATION AND VALIDATION OF ONE DIMENSIONAL MODELS USED IN SUBCOOLED FLOW BOILING ANALYSIS
2009 International Nuclear Atlantic Conference - INAC 2009 Rio de Janeiro, RJ, Brazil, September 27 to October 2, 2009 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 978-85-99141-03-8 VERIFICATION
More informationCoolant Flow and Heat Transfer in PBMR Core With CFD
Heikki Suikkanen GEN4FIN 3.10.2008 1/ 27 Coolant Flow and Heat Transfer in PBMR Core With CFD Heikki Suikkanen Lappeenranta University of Technology Department of Energy and Environmental Technology GEN4FIN
More informationModelling of Break-up and Coalescence in Bubbly Two-Phase Flows
Modelling of Break-up and Coalescence in Bubbly Two-Phase Flows Simon Lo and Dongsheng Zhang CD-adapco, Trident Park, Didcot OX 7HJ, UK e-mail: simon.lo@uk.cd-adapco.com Abstract Numerical simulations
More informationEasyChair Preprint. Numerical Simulation of Fluid Flow and Heat Transfer of the Supercritical Water in Different Fuel Rod Channels
EasyChair Preprint 298 Numerical Simulation of Fluid Flow and Heat Transfer of the Supercritical Water in Different Fuel Rod Channels Huirui Han and Chao Zhang EasyChair preprints are intended for rapid
More informationPREDICTION OF MASS FLOW RATE AND PRESSURE DROP IN THE COOLANT CHANNEL OF THE TRIGA 2000 REACTOR CORE
PREDICTION OF MASS FLOW RATE AND PRESSURE DROP IN THE COOLANT CHANNEL OF THE TRIGA 000 REACTOR CORE Efrizon Umar Center for Research and Development of Nuclear Techniques (P3TkN) ABSTRACT PREDICTION OF
More informationStatus and Future Challenges of CFD for Liquid Metal Cooled Reactors
Status and Future Challenges of CFD for Liquid Metal Cooled Reactors IAEA Fast Reactor Conference 2013 Paris, France 5 March 2013 Ferry Roelofs roelofs@nrg.eu V.R. Gopala K. Van Tichelen X. Cheng E. Merzari
More informationOnset of Flow Instability in a Rectangular Channel Under Transversely Uniform and Non-uniform Heating
Onset of Flow Instability in a Rectangular Channel Under Transversely Uniform and Non-uniform Heating Omar S. Al-Yahia, Taewoo Kim, Daeseong Jo School of Mechanical Engineering, Kyungpook National University
More informationNumerical modelling of direct contact condensation of steam in BWR pressure suppression pool system
Numerical modelling of direct contact condensation of steam in BWR pressure suppression pool system Gitesh Patel, Vesa Tanskanen, Juhani Hyvärinen LUT School of Energy Systems/Nuclear Engineering, Lappeenranta
More informationExperimental and Numerical Investigation of Two- Phase Flow through Enlarging Singularity
Purdue University Purdue e-pubs International Refrigeration and Air Conditioning Conference School of Mechanical Engineering 212 Experimental and Numerical Investigation of Two- Phase Flow through Enlarging
More informationBoiling and Condensation (ME742)
Indian Institute of Technology Kanpur Department of Mechanical Engineering Boiling and Condensation (ME742) PG/Open Elective Credits: 3-0-0-9 Updated Syllabus: Introduction: Applications of boiling and
More informationENGINEERING OF NUCLEAR REACTORS. Fall December 17, 2002 OPEN BOOK FINAL EXAM 3 HOURS
22.312 ENGINEERING OF NUCLEAR REACTORS Fall 2002 December 17, 2002 OPEN BOOK FINAL EXAM 3 HOURS PROBLEM #1 (30 %) Consider a BWR fuel assembly square coolant subchannel with geometry and operating characteristics
More informationNumerical Simulation of the MYRRHA reactor: development of the appropriate flow solver Dr. Lilla Koloszár, Philippe Planquart
Numerical Simulation of the MYRRHA reactor: development of the appropriate flow solver Dr. Lilla Koloszár, Philippe Planquart Von Karman Institute, Ch. de Waterloo 72. B-1640, Rhode-St-Genese, Belgium,
More informationResearch Article Numerical Study of the Steady-State Subchannel Test-Case with NEPTUNE CFD for the OECD/NRC NUPEC PSBT Benchmark
Science and Technology of Nuclear Installations Volume 212, Article ID 524598, 11 pages doi:1.1155/212/524598 Research Article Numerical Study of the Steady-State Subchannel Test-Case with NEPTUNE CFD
More informationABSTRACT. ROLLINS, CHAD ERIC. Development of Multiphase Computational Fluid Dynamics Solver in OpenFOAM. (Under the direction of Hong Luo.
ABSTRACT ROLLINS, CHAD ERIC. Development of Multiphase Computational Fluid Dynamics Solver in OpenFOAM. (Under the direction of Hong Luo.) From the viewpoint of an increase in energy demand, a shortage
More informationMixing and Evaporation of Liquid Droplets Injected into an Air Stream Flowing at all Speeds
Mixing and Evaporation of Liquid Droplets Injected into an Air Stream Flowing at all Speeds F. Moukalled* and M. Darwish American University of Beirut Faculty of Engineering & Architecture Mechanical Engineering
More informationOn the validity of the twofluid model for simulations of bubbly flow in nuclear reactors
On the validity of the twofluid model for simulations of bubbly flow in nuclear reactors Henrik Ström 1, Srdjan Sasic 1, Klas Jareteg 2, Christophe Demazière 2 1 Division of Fluid Dynamics, Department
More informationProgress and Challenges in Predictive Thermal Hydraulic Simulations
NSE Nuclear Science & Engineering at MIT science : systems : society Progress and Challenges in Predictive Thermal Hydraulic Simulations Massachusetts Institute of Technology Emilio Baglietto A new approach
More informationStudies on flow through and around a porous permeable sphere: II. Heat Transfer
Studies on flow through and around a porous permeable sphere: II. Heat Transfer A. K. Jain and S. Basu 1 Department of Chemical Engineering Indian Institute of Technology Delhi New Delhi 110016, India
More information