Fracture and Creep in an All- Tungsten Divertor for ARIES Jake Blanchard University of Wisconsin – Madison August 2012.

Slides:

Advertisements

Similar presentations

(a) Fracture Behavior Computer Simulation (d) Lab Testing

Advertisements

NEEP 541 Design of Irradiated Structures Fall 2002 Jake Blanchard.

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

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.

Design of Machine Elements

ASIPP HT-7 & EAST 17 th International Conference on Plasma Surface Interactions in Controlled Fusion Devices, May, 2006, Hefei China H.Li Presented.

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,

September 24-25, 2003 HAPL meeting, UW, Madison 1 Armor Configuration & Thermal Analysis 1.Parametric analysis in support of system studies 2.Preliminary.

Example: Microrobot leg 3D. Introduction This model shows the movement of a silicon micro-robot leg due to thermal expansion as a function of time. The.

Page 1 of 14 External Transition Joints for Tungsten Divertors D. Navaei, X. R. Wang, M. S. Tillack and the ARIES Team Japan-US Workshop on Fusion Power.

Japan-US Workshop held at San Diego on April 6-7, 2002 How can we keep structural integrity of the first wall having micro cracks? R. Kurihara JAERI-Naka.

BARTOSZEK ENGINEERING 1 Review of the Stress Analysis of the MiniBooNE Horn MH1 Larry Bartoszek, P.E. 1/20/00 BARTOSZEK ENGINEERING.

Design of an Aerospace Component

Japan PFC/divertor concepts for power plants. T retention and permeation  Problems of T retention would not be serious…. Wall temperature will exceeds.

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.

Integrated Effects of Disruptions and ELMs on Divertor and Nearby Components Valeryi Sizyuk Ahmed Hassanein School of Nuclear Engineering Center for Materials.

May 28-29, 2008/ARR 1 Thermal Effect of Off-Normal Energy Deposition on Bare Ferritic Steel First Wall A. René Raffray University of California, San Diego.

Scoping Study of He-cooled Porous Media for ARIES-CS Divertor Presented by John Pulsifer Major contributor: René Raffray University of California, San.

June19-21, 2000Finalizing the ARIES-AT Blanket and Divertor Designs, ARIES Project Meeting/ARR ARIES-AT Blanket and Divertor Design (The Final Stretch)

Heat Flux Gradient Limits for Liquid-Protected Divertors S. I. Abdel-Khalik, S. Shin, and M. Yoda ARIES Meeting, San Diego (Nov 4-5, 2004) G. W. Woodruff.

Ge277-Experimental Rock Friction implication for seismic faulting Some other references: Byerlee, 1978; Dieterich, 1979; Ruina, 1983; Tse and Rice, 1986;

M. Yoda, S. I. Abdel-Khalik, D. L. Sadowski and M. D. Hageman Woodruff School of Mechanical Engineering Extrapolating Experimental Results for Model Divertor.

Fracture of Divertor Structures Jake Blanchard ARIES Meeting April 2011.

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

Unsteady Heat Transfer in Semi-infinite Solids Solidification process of the coating layer during a thermal spray operation is an unsteady heat transfer.

FETS-HIPSTER (Front End Test Stand – High Intensity Proton Source for Testing Effects of Radiation) Proposal for a new high-intensity proton irradiation.

Field Validation and Parametric Study of a Thermal Crack Spacing Model David H. Timm - Auburn University Vaughan R. Voller - University of Minnesota Presented.

Fracture and Creep in the All-Tungsten ARIES Divertor

Wear-Mapping to Optimise Overlay Coating Design in Rolling Sliding Contacts R. Ahmed Heriot-Watt University, United Kingdom.

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.

How do we deal with the power/energy fluxes we have derived for ELMs, disruptions or others C. Kessel, PPPL ARIES Project Meeting, Jan 23-24, 2012, UCSD.

Fracture of Tungsten in a HAPL Chamber Jake Blanchard HAPL MWG Fusion Technology Institute University of Wisconsin September 2003.

O AK R IDGE N ATIONAL L ABORATORY U. S. D EPARTMENT OF E NERGY 1 Tungsten Armored Ferritic Steel Glenn Romanoski & Lance Snead June 2004.

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

Plan to Develop A First Wall Concept for Laser IFE.

06-November-2013 Thermo-Mechanical Tests BE-RF-PM Review of the CLIC Two-Beam Module Program Thermo-Mechanical Tests L. Kortelainen, I. Kossyvakis, R.

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

July 11, 2003 HAPL e-meeting. 1 Armor Design & Modeling Progress A. René Raffray UCSD HAPL e-meeting July 11, 2003 (1)Provide Parameters for Chamber “System”

John R. Hopper Leibniz Institute for Marine Science, Kiel, Germany Thomas K. Nielsen Maersk Olie og Gas A/S,

Update on Roughening Work Jake Blanchard HAPL MWG Fusion Technology Institute University of Wisconsin e-meeting – July 2003.

Heat Loading in ARIES Power Plants: Steady State, Transient and Off-Normal C. E. Kessel 1, M. A. Tillack 2, and J. P. Blanchard 3 1 Princeton Plasma Physics.

Page 1 of 15 Robust High-Performance First Wall Design and Analysis X. R. Wang, S. Malang, M. S. Tillack and the ARIES Team Japan-US Workshop on Fusion.

Forschungszentrum Karlsruhe FZK - EURATOM ASSOCIATION 05/14/2005 Thomas Ihli 1 Status of He-cooled Divertor Design Contributors: A.R. Raffray, and The.

The tungsten/F82H sample was impinged at 6 different locations with 6 different laser fluence energies to determine the critical energy that would result.

Helium-Cooled Divertor Options and Analysis

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,

Operating Windows in Tungsten- Coated Steel Walls Jake Blanchard – MWG Greg Moses, Jerry Kulcinski, Bob Peterson, Don Haynes - University of Wisconsin.

Session 3.2: Material – PMI and High Heat Flux Testing R. Neu: Recent PMI Experience in Tokamaks R. Doerner: PMI Issues beyond ITER M. Roedig: High Heat.

Page 1 of 9 ELM loading conditions and component responses C. Kessel and M. S. Tillack ARIES Project Meeting 4-5 April 2011.

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.

ARIES Meeting University of Wisconsin, April 27 th, 2006 Brad Merrill, Richard Moore Fusion Safety Program Update of Pressurization Accidents in ARIES-CS.

G.Kurevlev - Manchester meeting1 Collimators Material Damage Study Previous results In our group - Adriana Bungau’s thesis - heat deposition on.

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.

Produktentwicklung und Maschinenelemente

Date of download: 11/1/2017 Copyright © ASME. All rights reserved.

Integrated Design: APEX-Solid Wall FW-Blanket

C. E. Kessel1, M. S. Tillack2, and J. P. Blanchard3

Modified Design of Aries T-Tube Divertor Concept

Valeryi Sizyuk Ahmed Hassanein School of Nuclear Engineering

Heat Conduction in Solids

Thin-Film Mechanics.

Update on Fracture Analyses

Advances in predictive thermo-mechanical modelling for the JET divertor experimental interpretation, improved protection, and reliable operation D. Iglesias,

Figure 4. Temperature Distribution within the workpiece domain

R1 Fillet Would like to find the stress fillet region.

First Wall Response to the 400MJ NRL Target

Li I light from DiMES during locked mode (Dt ~ 16 ms)

Presentation transcript:

Fracture and Creep in an All- Tungsten Divertor for ARIES Jake Blanchard University of Wisconsin – Madison August 2012

Introduction The ARIES Project is exploring the feasibility of using tungsten as a structural material for plasma-facing components For now, we are assuming the material is pure tungsten, but alloys may be necessary This talk addresses two key failure modes that must be addressed by these designs ◦ Fracture ◦ Thermal creep

The Design

Major Input Parameters ParameterValueUnits Surface Heat11MW/m 2 Volumetric Heating17.5MW/m 3 Coolant Pressure10MPa Bulk Coolant Temperature 600C

Crack Location Crack-Free Stress State Finite Element Model with Crack on Coolant Channel Surface

Fracture Results Results for Crack on Previous Slide Results for Crack Perpendicular to Cracks Shown Results for Crack in Notch (at shutdown)

Effect of Transients Surface Temperature Temperature 2.5 mm below surface Vary nominal heat flux by +/-20% and apply 20 cycles No discernible variation below surface

Surface Effect of “Small” ELM Assume 1.95 MJ deposited on divertor surface over 1.2 milliseconds Melt layer is 20 microns thick

Thermal Creep Add Thermal Creep Model for Tungsten Creep rates are excessive at 11 MW/m 2 Nominal Heat Flux Reduced Heat Flux

Design Modifications Varying Surface Heating or Coolant Pressure Reducing Notch Depth

Conclusions We have not identified any “show- stoppers” with respect to an all-tungsten divertor for ARIES Many uncertainties are still unresolved