He-cooled Divertor Design Approach

Slides:



Advertisements
Similar presentations
Further Modifications to the ARIES T-tube Divertor Concept Jeremy Burke ARIES-Pathways Project Meeting Jan 26,
Advertisements

Introduction to Plasma-Surface Interactions Lecture 6 Divertors.
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.
External Convection: Laminar Flat Plate
CFD and Thermal Stress Analysis of Helium-Cooled Divertor Concepts Presented by: X.R. Wang Contributors: R. Raffray and S. Malang University of California,
High Performance Divertor Target Plate, a Combination of Plate and Finger Concepts S. Malang, X.R. Wang ARIES-Pathway Meeting Georgia Institute of Technology,
U PDATES ON D ESIGN AND A NALYSES OF THE P LATE -T YPE D IVERTOR X.R. Wang 1, S. Malang 2, M. S. Tillack 1 1 University of California, San Diego, CA 2.
D ESIGN I MPROVEMENTS OF THE W-B ASED D IVERTOR C ONCEPTS X.R. Wang 1, S. Malang 2, M. S. Tillack 1, J. Burke 1 University of California, San Diego, CA.
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.
March 21-22, 2006 HAPL meeting, ORNL 1 Status of Chamber and Blanket Effort A. René Raffray UCSD With contributions from: M. Sawan B. Robson G. Sviatoslavsky.
First Wall Thermal Hydraulics Analysis El-Sayed Mogahed Fusion Technology Institute The University of Wisconsin With input from S. Malang, M. Sawan, I.
June 14-15, 2005/ARR 1 Status of ARIES-CS Power Core Engineering A. René Raffray University of California, San Diego ARIES Meeting UW June 14-15, 2005.
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.
Experimental Verification of Gas- Cooled T-Tube Divertor Performance L. Crosatti, D. Sadowski, S. Abdel-Khalik, and M. Yoda ARIES Meeting, UCSD (June 14-15,
April 27-28, 2006/ARR 1 Support and Possible In-Situ Alignment of ARIES-CS Divertor Target Plates Presented by A. René Raffray University of California,
February 24-25, 2005/ARR 1 ARIES-CS Power Core Engineering: Status and Next Steps A. René Raffray University of California, San Diego ARIES Meeting GA.
External Flow: Flow over Bluff Objects (Cylinders, Sphere, Packed Beds) and Impinging Jets.
Experimental Validation of Thermal Performance of Gas-Cooled Divertors By S. Abdel-Khalik, M. Yoda, L. Crosatti, E. Gayton, and D. Sadowski International.
Japan considerations on design and qualification of PFC's for near term machines (ITER) Satoshi Suzuki 1, Satoshi Konishi 2 1 Japan Atomic Energy Agency.
Scoping Study of He-cooled Porous Media for ARIES-CS Divertor Presented by John Pulsifer Major contributor: René Raffray University of California, San.
M. Yoda, S. I. Abdel-Khalik, D. L. Sadowski, B. H. Mills, and J. D. Rader G. W. Woodruff School of Mechanical Engineering Parametric Design Curves for.
June19-21, 2000Finalizing the ARIES-AT Blanket and Divertor Designs, ARIES Project Meeting/ARR ARIES-AT Blanket and Divertor Design (The Final Stretch)
Status of the ARIES-CS Power Core Configuration and Maintenance Presented by X.R. Wang Contributors: S. Malang, A.R. Raffray ARIES Meeting PPPL, NJ Sept.
Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft 02/24/2005 T. Ihli PL FUSION FZK - EURATOM ASSOCIATION 1 He-cooled Divertor Development in the.
M. Yoda, S. I. Abdel-Khalik, D. L. Sadowski and M. D. Hageman Woodruff School of Mechanical Engineering Extrapolating Experimental Results for Model Divertor.
March 20-21, 2000ARIES-AT Blanket and Divertor Design, ARIES Project Meeting/ARR Status ARIES-AT Blanket and Divertor Design The ARIES Team Presented.
Chapter 7 Sections 7.4 through 7.8
Cooling Update (May 2011) Tim. Overview From last time – Estimate Power Loads Active components Extraneous heat sources – Develop methodology for exploring.
Maintenance Schemes for a DEMO Power Plant and related DCLL Designs Siegfried Malang 2 nd EU-US DCLL Workshop2 nd EU-US DCLL Workshop University of California,University.
Fracture and Creep in the All-Tungsten ARIES Divertor
ASIPP EAST Overview Of The EAST In Vessel Components Upgraded Presented by Damao Yao.
M. Yoda, S. I. Abdel-Khalik, D. L. Sadowski and M. D. Hageman Woodruff School of Mechanical Engineering Update on Thermal Performance of the Gas- Cooled.
M. Yoda, S. I. Abdel-Khalik, D. L. Sadowski, B. H. Mills, and J. D. Rader G. W. Woodruff School of Mechanical Engineering Updated Thermal Performance of.
M. Yoda, S. I. Abdel-Khalik, D. L. Sadowski, M. D. Hageman, B. H. Mills, and J. D. Rader G. W. Woodruff School of Mechanical Engineering Extrapolating.
Engineering Overview of ARIES-ACT1 M. S. Tillack, X. R. Wang and the ARIES Team Japan/US Workshop on Power Plant Studies and Advanced Technologies
ITER test plan for the solid breeder TBM Presented by P. Calderoni March 3, 2004 UCLA.
U PDATED ARIES-ACT P OWER C ORE D EFINITION AND S I C B LANKET X.R. Wang, M. S. Tillack, S. Malang F. Najmabadi and L.A. El-Guebaly ARIES-Pathways Project.
Convection: Internal Flow ( )
Forschungszentrum Karlsruhe FZK - EURATOM ASSOCIATION 05/14/2005 Thomas Ihli 1 Status of He-cooled Divertor Design Contributors: A.R. Raffray, and The.
P LATE -T YPE D IVERTOR 3D P RINTING X.R. Wang D. Navaei ARIES-Pathways Project Meeting Gaithersburg, MD May 31-June 1, 2012.
Helium-Cooled Divertor Options and Analysis
Update on ARIES ACT2 Power Core Design and Engineering X. R. Wang, M. S. Tillack, C. Koehly ARIES Project Meeting 18 September2013 ARIES UC San Diego UW.
Page 1 of 17 Evaluation of high heat flux components under normal and off-normal conditions M. S. Tillack with contributions from X. Wang, A. R. Raffray,
DCLL ½ port Test Blanket Module thermal-hydraulic analysis Presented by P. Calderoni March 3, 2004 UCLA.
Page 1 of 8 Concept development of pin-fin cooled divertors M. S. Tillack ARIES Project Meeting July 2010.
Mitglied der Helmholtz-Gemeinschaft Jörg Wolters, Michael Butzek Focused Cross Flow LBE Target for ESS 4th HPTW, Malmö, 3 May 2011.
External Flow: The Flat Plate in Parallel Flow Chapter 7 Section 7.1 through 7.3.
1 A Self-Cooled Lithium Blanket Concept for HAPL I. N. Sviatoslavsky Fusion Technology Institute, University of Wisconsin, Madison, WI With contributions.
Heat Transfer Su Yongkang School of Mechanical Engineering # 1 HEAT TRANSFER CHAPTER 7 External flow.
Page 1 of 19 Design Improvements and Analysis to Push the Heat Flux Limits of Divertors M. S. Tillack, X. R. Wang, J A. Burke and the ARIES Team Japan-US.
HL-LHC-UK Thermal Shield Update Niklas Templeton 07/03/2016.
SPS High Energy LSS5 Thermal contact & cooling aspects
ARIES ACT1 Power Core Engineering M. S. Tillack, X. R. Wang, F. Najmabadi, S. Malang and the ARIES Team ANS 20 th Topical Meeting on the Technology of.
Chopper Beam Dump Thermal Problem 10/27/20101PX Linac FE Technical Discussions.
Thermal-hydraulic analysis of unit cell for solid breeder TBM
DCLL TBM Reference Design
X.R. Wang, M. S. Tillack, S. Malang, F. Najmabadi and the ARIES Team
Date of download: 11/7/2017 Copyright © ASME. All rights reserved.
Integrated Design: APEX-Solid Wall FW-Blanket
Trade-Off Studies and Engineering Input to System Code
Modified Design of Aries T-Tube Divertor Concept
DCLL TBM Design Status, Current and future activities
Heat Transfer Coefficient
Overview of mechanical design & construction
Status of ARIES-CS Power Core Engineering
Status of the ARIES Program
ARIES-CS Power Core Engineering: Status and Next Steps
University of California, San Diego
Presentation transcript:

He-cooled Divertor Design Approach Presented by Thomas Ihli * Contributors: A.R. Raffray, and The ARIES Team ARIES Meeting General Atomics, San Diego February 24-25, 2005 * Forschungszentrum Karlsruhe, currently exchange visitor to UCSD & The ARIES Team

BASIC W – DIVERTOR DESIGN CONCEPTS Tungsten caps (current European concepts HEMJ, HEMS, HETS) Tungsten tubes (new alternative concept: Tungsten T-Tube Divertor) Tungsten plates (e.g. former FZK designs)  Different heat transfer enhancement techniques possible for all concepts

Do we need a flat target surface ? Round tubes have to be oriented in direction of the field lines Otherwise: excessive shadowing  shadowing  free orientation Flat target surface is favorable sacrificial layer thickness for Compact Stellerator : tbd

Long tubes or tube segments ? Small wall thickness for low temperature gradients and high cooling performance  small diameter (e.g. 15 mm)  limited mass flow Parts from brittle materials should be small to reduce probability of failure (test before assembly) Flexible structure for low thermal stress levels Uniform heat load for parts favorable dT ~ 100 K/mm at 10 MW/m2  Tube segments

Connection of tube segments ? He velocity  deformation  A) Series connection B) U-Tubes in parallel Different thermal expansions  Short tubes might be possible C) L-Tubes in parallel most promising D) T-Tubes in parallel

General design of the T junction ?  Bulge for oval section σmax ~ 670 MPa 3Sm at 1100°C ~ 460 MPa at 850°C ~ 580 MPa  stress peaks at T junction σmax ~ 530 Mpa  rectangular connector with drilling o.k. σmax ~ 350 MPa q = 10 MW/m2 p = 10 MPa h = 20 kW/m2K

Reasonable T connector length ? σmax ~ 360 MPa 30 mm no stress peak at drilling: σdr ~ 170 MPa σmax ~ 340 MPa no stress peak at drilling: σdr ~ 185 MPa 25 mm σmax ~ 320 MPa stress peak at drilling: σdr ~ 360 MPa 20 mm q = 10 MW/m2 p = 10 MPa h = 20 kW/m2K

Reasonable tube length ? length stress intensity deformation (Δz) angle variation He velocity [mm] [MPa] [mm] along tube [m/s] 100 368 0.175 ± 0.10° 62 150 367 0.385 ± 0.15° 94 250 366 1.155 ± 0.26° 157 L = 100 mm; D = 15 mm Deformation [ mm ] 0.155 -0.090 L = 150 mm; D = 15 mm Deformation [ mm ] 0.155 -0.311 L = 250 mm; D = 15 mm Deformation [ mm ] 0.155 - 1.014

Detailed design of the T junction Stress Intensity [ MPa ] 360 T-connector with central inlet and two outlet sections: + Large cross section + Low stress levels 200 25 mm 150 mm Option: L = 150 mm; D = 15 mm

W – Fe transition ? Tungsten W-Fe Gradient Steel anchor W-FE gradient transition: Slices for stepwise adjusting of thermal expansion, Brazed and/or HIPped Tungsten W-Fe Gradient Steel anchor

Tube end design ?  Heat loaded caps critical Shielded caps favorable tor. rad.

Heat transfer enhancement Jet Impingement

Heat transfer enhancement Cartridge W-Tube Layout example: jet slot width: 0.4 mm jet-wall-spacing: 1.2 mm specific mass flow: 2.12 g/cm2 mass flow per tube: 48 g p = 10 MPa, dp ~ 0.11 MPa dT ~ 90 K at 10 MW/m2

Layout Example jet slot width: 0.4 mm jet-wall-spacing: 1.2 … 1.6 mm specific mass flow: 2.12 g/cm2 mass flow per tube: 48 g p = 10 MPa, dp ~ 0.11 MPa dT ~ 90 K at 10 MW/m2 THe ~ 605 … 695°C Tmax ~ 1370°C Tmax ~ 1240°C

General T-Tube Design Armor Layer (W) Cartridge (Densimet 18) Tube (W-Alloy) Cartridge (Densimet 18) Cap (W-Alloy) Armor Layer (W) Connector part 1 (W-Alloy or Densimet 18) Connector part 2 (Slices from W to Steel) Connector part 3: anchor (ferritic steel)

General Module Design Support channel (Steel) Insert (Steel) T-Tubes (W) Insert (Steel) pol. tor. rad. General Module Design

Considerations and further Objectives The new T-Tube design seems to be a promising alternative concept: Thermal stress within design limits for 10 MW/m2 Simple manifolding concept possible Simple slot based jet impingement sufficient Next steps: Additional considerations on alternative geometry options e.g. tungsten plates Manifolding/integration concept for ARIES CS