DL Youchison 5931/31.02 1 Boiling Heat Transfer in ITER First Wall Hypervapotrons Dennis Youchison, Mike Ulrickson and Jim Bullock Sandia National Laboratories.

Slides:

Advertisements

Similar presentations

CFD Analysis for ITER FW/Shield Designs Alice Ying, Ryan Hunt, Hongjie Zhang (UCLA) Dennis Youchison James Bullock, Mike Ulrickson (SNL) July 8, 2009 MIT,

Advertisements

Karl J.L. Geisler, Ph.D. Buoyancy-Driven Two Phase Flow and Boiling Heat Transfer in Narrow Vertical Channels CFD Simulation.

IMPACT CAPE-P: DNB Power Analysis Code for PWR FUEL Assembly - Evaluation Method - Analytical Step Calculation Method 3. Detection of DNB 1. Fuel Bundle.

SolidWorks Flow Simulation

Ss Hefei, China July 19, 2011 Nuclear, Plasma, and Radiological Engineering Center for Plasma-Material Interactions Contact: Flowing.

First Wall Heat Loads Mike Ulrickson November 15, 2014.

Sandia is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy’s National Nuclear.

Two-Phase Flow Boiling Heat Transfer P M V Subbarao Professor Mechanical Engineering Department Selection of Optimal Parameters for Healthy and Safe Furnace.

Cryogenic Experts Meeting (19 ~ ) Heat transfer in SIS 300 dipole MT/FAIR – Cryogenics Y. Xiang, M. Kauschke.

Lecture Objectives -Finish with modeling of PM -Discuss -Advance discretization -Specific class of problems -Discuss the CFD software.

2003 International Congress of Refrigeration, Washington, D.C., August 17-22, 2003 CFD Modeling of Heat and Moisture Transfer on a 2-D Model of a Beef.

5931/ / PFC Meeting D.L. Youchison, M.A. Ulrickson, J.H. Bullock Sandia National Laboratories Sandia is a multiprogram laboratory operated.

CFD and Thermal Stress Analysis of Helium-Cooled Divertor Concepts Presented by: X.R. Wang Contributors: R. Raffray and S. Malang University of California,

1 “CFD Analysis of Inlet and Outlet Regions of Coolant Channels in an Advanced Hydrocarbon Engine Nozzle” Dr. Kevin R. Anderson Associate Professor California.

Boiling Chapter 10 Sections 10.1 through General Considerations Boiling is associated with transformation of liquid to vapor at a solid/liquid interface.

Two-Phase: Overview Two-Phase Boiling Condensation

Thermo Fluid Design Analysis of TBM cooling schemes M. Narula with A. Ying, R. Hunt, S. Park ITER-TBM Meeting UCLA Feb 14-15, 2007.

Unstructured Data Partitioning for Large Scale Visualization CSCAPES Workshop June, 2008 Kenneth Moreland Sandia National Laboratories Sandia is a multiprogram.

Two-Phase Heat Transfer Laboratory Texas A&M University Experimental Study of Condensation on Micro Grooved Plates R. Barron-jimenez, H. Y. Hu, G. P. Peterson.

First Wall Thermal Hydraulics Analysis El-Sayed Mogahed Fusion Technology Institute The University of Wisconsin With input from S. Malang, M. Sawan, I.

Thermo-fluid Analysis of Helium cooling solutions for the HCCB TBM Presented By: Manmeet Narula Alice Ying, Manmeet Narula, Ryan Hunt and M. Abdou ITER.

Thermal Analysis of Helium- Cooled T-tube Divertor S. Shin, S. I. Abdel-Khalik, and M. Yoda ARIES Meeting, Madison (June 14-15, 2005) G. W. Woodruff School.

Preliminary Assessment of Porous Gas-Cooled and Thin- Liquid-Protected Divertors S. I. Abdel-Khalik, S. Shin, and M. Yoda ARIES Meeting, UCSD (March 2004)

The shield block is a modular system made up of austenitic steel SS316 LN-IG whose main function is to provide thermal and nuclear shielding of outer components.

University of South Carolina FCR Laboratory Dept. of Chemical Engineering By W. K. Lee, S. Shimpalee, J. Glandt and J. W. Van Zee Fuel Cell Research Laboratory.

Image courtesy of National Optical Astronomy Observatory, operated by the Association of Universities for Research in Astronomy, under cooperative agreement.

Single and multi-phase flows through rock fractures occur in various situations, such as transport of dissolved contaminants through geological strata,

Computation of FREE CONVECTION P M V Subbarao Associate Professor Mechanical Engineering Department IIT Delhi Quantification of Free …….

March 20-21, 2000ARIES-AT Blanket and Divertor Design, ARIES Project Meeting/ARR Status ARIES-AT Blanket and Divertor Design The ARIES Team Presented.

Verification and Validation Diagram of a Control Rod Guide Tube on top of a hot box dome that has been gradually heating up. A hole was drilled here to.

KIT – University of the State of Baden-Wuerttemberg and National Research Center of the Helmholtz Association Institute for Nuclear and Energy Technologies.

Heat and Mass Transfer Laboratory

1 CREL meeting 2004 CFD Simulation of Fisher-Tropsch Synthesis in Slurry Bubble Column By Andrey Troshko Prepared by Peter Spicka Fluent Inc. 10 Cavendish.

1 Calorimeter Thermal Analysis with Increased Heat Loads September 28, 2009.

Two-Phase Heat Transfer Lab May 28-30, Analytical And Experimental Investigation of Evaporation from Porous Capillary Structures Presented to ONR.

Pressure drop prediction models o Garimella et al. (2005) o Considered parameters o Single-phase pressure gradients o Martinelli parameter o Surface tension.

Lesson 16 BOILING HEAT TRANSFER

Brookhaven Science Associates U.S. Department of Energy MUTAC Review April , 2004, LBNL Target Simulation Roman Samulyak, in collaboration with.

A culvert representing the fuselage of an airplane was positioned 1 m downwind of the fuel pan (Figs. 2 and 3). The culvert had a nominal diameter of 2.7.

Evaporation/boiling Phenomena on Thin Capillary Wick Yaxiong Wang Foxconn Thermal Technology Inc., Austin, TX Chen Li G. P. Peterson Rensselaer Polytechnic.

ITER test plan for the solid breeder TBM Presented by P. Calderoni March 3, 2004 UCLA.

Work Plans for FY06 Sandia National Laboratories Michael Ulrickson Presented at PFC Technology Meeting May 9-11, 2005 At PPPL Sandia is a multiprogram.

High flux heat transfer in a target environment T.Davenne High Power Targets Group Rutherford Appleton Laboratory Science and Technology Facilities Council.

Lesson 13 CONVECTION HEAT TRANSFER Given the formula for heat transfer and the operating conditions of the system, CALCULATE the rate of heat transfer.

Lecture Objectives Unsteady State Simulation Example Modeling of PM.

1 Parametric Thermal-Hydraulic Analysis of TBM Primary Helium Loop Greg Sviatoslavsky Fusion Technology Institute, University of Wisconsin, Madison, WI.

HIGH HEAT FLUX PEAKING FACTORS AND ENHANCEMENT Ronald D. Boyd Sr., PhD, PE, PI Distinguished Professor, Honeywell Professor, Director of the Thermal Science.

US Test Blanket Module Partially Integrated Testing Sandia is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for.

Lecture Objectives -Finish Particle dynamics modeling -See some examples of particle tracking -Eulerian Modeling -Define deposition velocity -Fluid Dynamics.

Analysis of Flow Boiling

Investigation of Thin Film Evaporation Limit in Single Screen Mesh Layers Presented to IMECE 2002 Nov. 19, 2002, New Orleans, LA Yaxiong Wang & G.P. “Bud”

Heat Transfer Su Yongkang School of Mechanical Engineering # 1 HEAT TRANSFER CHAPTER 6 Introduction to convection.

CFD Simulation Investigation of Natural Gas Components through a Drilling Pipe RASEL A SULTAN HOUSSEMEDDINE LEULMI.

CERN Cryolab CO 2 cooling for pixel detectors Investigation of heat transfer Christopher Franke, Torsten Köttig, Jihao Wu, Friedrich Haug TE-CRG-CI.

Numerical Investigation of Flow Boiling in Double-layer Microchannel Heat Sink.

Thermal-hydraulic analysis of unit cell for solid breeder TBM

CFD ANALYSIS OF MULTIPHASE TRANSIENT FLOW IN A CFB RISER

Titolo presentazione sottotitolo

From: On Development of a Semimechanistic Wall Boiling Model

Xiaomin Pang, Yanyan Chen, Xiaotao Wang, Wei Dai, Ercang Luo

Influence on the performance of cryogenic counter-flow heat exchangers due to longitudinal conduction, heat in-leak and property variations Qingfeng Jiang.

The inner flow analysis of the model

Date of download: 12/23/2017 Copyright © ASME. All rights reserved.

Lecture Objectives Learn about particle dynamics modeling

Modified Design of Aries T-Tube Divertor Concept

Phoebus 2A, Nuclear Thermal Element

Thermal behavior of the LHCb PS VFE Board

Lecture Objectives: Start using CFD Software Class project 1

Chapter 10 Sections 10.1 through 10.5

Sample Applications of Fluent to Multiphase Flows

Presentation transcript:

DL Youchison 5931/ Boiling Heat Transfer in ITER First Wall Hypervapotrons Dennis Youchison, Mike Ulrickson and Jim Bullock Sandia National Laboratories Albuquerque, NM August 6, 2010 FNST/MASCO/PFC Meeting Sandia is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy’s National Nuclear Security Administration under contract DE-AC04-94AL85000.

DL Youchison 5931/ Outline What are hypervapotrons? Why hypervapotrons? Geometry optimization Boiling heat transfer in hypervapotrons –Why CFD? Benchmarking with HHF test data CHF prediction

DL Youchison 5931/ Star-CCM+ Version , User Guide, CD-adapco, Inc., New York, NY USA (2010). S. Lo and A. Splawski, “Star-CD Boiling Model Development”, CD-adapco, (2008). D.L. Youchison, M.A. Ulrickson, J.H. Bullock, “A Comparison of Two-Phase Computational Fluid Dynamics Codes Applied to the ITER First Wall Hypervapotron,” IEEE Trans. On Plasma. Science, 38 7, (2010). Upcoming paper in the 2010 TOFE. Background

DL Youchison 5931/ ITER First Wall 04

DL Youchison 5931/ Why hypervapotrons? Advantages: High CHF with relatively lower pressure drop Reduction in E&M loads due to thin copper faceplate Lower Cu/Be interface temperature (no ss liners) Less bowing of fingers due to thermal loads Disadvantages: CuCrZr/SS316LN UHV joint exposed to water

DL Youchison 5931/ What are hypervapotrons? Hypervapotron FW “finger”

DL Youchison 5931/ Two-phase CFD in water-cooled PFCs Problem: conjugate heat transfer with boiling Focus on nucleate boiling regime below critical heat flux Use Eulerian multiphase model in FLUENT & Star-CCM+ RPI model (Bergles&Rohsenow) Features heat and mass transfer between liquid and vapor, custom drag law, lift or buoyancy and influence of bubbles on turbulence CCM+ transitions to a VOF model for the film when vapor fraction is high enough – need to know when to initiate VOF

DL Youchison 5931/ Velocity distributions 5 MW/m g/s t=2.05s Drag on bubbles, lift or buoyancy, changes in viscosity and geometry, all affect the velocity distribution under the heated zone. 2mm-deep teeth and 3-mm spacing optimized to produce a simple reverse eddy in the groove.

DL Youchison 5931/ Star-CCM+ 560 k polyhedra mesh Switches from Eulerian multi-phase mixture to VOF for film boiling.

DL Youchison 5931/ CCM+ boiling models were benchmarked against US and Russian test data for rectangular channels and hypervapotrons to within 10 o C. capability to predict CHF from CFD Star-CCM+ Results Surface temperature distribution, t=6.3 s Case analyzed is a hot “stripe” on a section of the ITER first wall.

DL Youchison 5931/ With no boiling, heat transfer is highest under the fins With boiling, the vapor fraction in grooves is 4%-6% on average t=6.3 s Star-CCM+ Results Case analyzed is a hot “stripe” on a section of the ITER first wall. The details of the heat transfer change dramatically as boiling ensues. Iso-surface of 2% vapor volume fraction

DL Youchison 5931/ Star-CCM+ gives same h as Fluent for nucleate boiling. Heat transfer coefficients increase in grooves where boiling takes place ranging from 12,000 to 13,000 W/m 2 K.

DL Youchison 5931/ Systematic parameter study performed on rectangular channels – then applied to hypervapotrons.

DL Youchison 5931/ Temperature (C) Thermocouple response 3.5 MW/m 2 through 6 s Russian data Thermocouple response 4.0 MW/m 2 through 6 s Temperature (C) ICHF 400 C Not ss yet! Rectangular channel results

15 Russian HV CHF Mock-up flow

16 Total of 490k poly cells in mesh Heated area is 100 mm x 48 mm 3 prism layers

17 Surface temperature – 6.0 MW/m 2, 1 m/s 115 C inlet, 2 MPa

18 CCM+ solid/fluid interface temperatures for 6.0 MW/m

19 Vapor fraction – 6.0 MW/m

20 Thermocouple response through 6 s Russian data 4 s for TCs to ss

21 Outlet temperature close to steady state.

DL Youchison 5931/ a)sub-cooled b)nucleate to transition boiling c)film boiling d)sub-cooled All flow regimes can exist simultaneously. 4.0 MW/m o C, 2 MPa water 1.0 m/s T: h:

DL Youchison 5931/ CHF Testing Testing of the HV mock-up Water 2 m/s P abs 10 MW/m 2 t puls 300s T/C (1.5 mm from CuCrZr surface) Second pulse at 10 MW/m 2 ) ICHF !