Swiss Industries - 20 th June 2012 1 Divertor and Blanket Systems: Design, Required technologies and Schedule M. Merola Head of the Internal Components.

Slides:



Advertisements
Similar presentations
Codes & Standards.
Advertisements

Frame design Status TB-SWG May 2005 Presented by K. Ioki Prepared by M. Morimoto VV and Blanket Division, ITER Garching ITER.
First Wall Heat Loads Mike Ulrickson November 15, 2014.
ASIPP EAST Tungsten-copper Divertor Development For EAST Present by D. -M. Yao EAST-Divertor Group, ASIPP-Hefei, China 25 th Symposium on Fusion Engineering.
PhD studies report: "FUSION energy: basic principles, equipment and materials" Birutė Bobrovaitė; Supervisor dr. Liudas Pranevičius.
High Performance Divertor Target Plate, a Combination of Plate and Finger Concepts S. Malang, X.R. Wang ARIES-Pathway Meeting Georgia Institute of Technology,
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.
September 15-16, 2005/ARR 1 Status of ARIES-CS Power Core and Divertor Design and Structural Analysis A. René Raffray University of California, San Diego.
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.
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,
11 th AFPA ITER In vessel Components P. Chappuis Guilin 1 st to 4 th Nov Slide 1 Philippe Chappuis IO Blanket Lead Engineer On Behalf of the ITER.
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.
The main function of the divertor is minimizing the helium and impurity content in the plasma as well as exhausting part of the plasma thermal power. The.
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.
March 20-21, 2000ARIES-AT Blanket and Divertor Design, ARIES Project Meeting/ARR Status ARIES-AT Blanket and Divertor Design The ARIES Team Presented.
NIOWAVE Requirements for Manufacturing Readiness: (Beamtube Assembly only) Due 1 month before start of manufacturing for CERN approval.
FNSF Maintenance and Research Strategy Siegfried Malang and Mohamed Abdou FNST Meeting held at UCLA, August 3, 2010.
Dr. Michael Peiniger Superconducting RF activities at RI Research Instruments with a focus on EXFEL cavity production.
S Temple CLRC1 End-cap Mechanics FDR Cooling Structures Steve Temple, RAL 1 November 2001.
Power Extraction Research Using a Full Fusion Nuclear Environment G. L. Yoder, Jr. Y. K. M. Peng Oak Ridge National Laboratory Oak Ridge, TN Presentation.
Construction of Wendelstein 7-X Max-Planck-Institut für Plasmaphysik
Prototype Divertor System: Steels and Fabrication Technologies Sameer Khirwadkar (Prototype Divertor Development Division) 21-July-2008 Institute for Plasma.
Status report on “Industrialization studies” at LAL on power couplers for XFEL _____ TILC08 – Tohoku University 3-6 March 2008 Sendai - Japan G. Wormser.
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.
ISFNT-11, Barcelona, Spain, September 16-20, 2013 © 2013, ITER Organization Slide 1 De sign, Fabrication and Testing of the ITER First Wall and Shielding.
1 SOFE, Chicago, IL, June 27, 2011 Design of the ITER First Wall and Blanket A. René Raffray, Mario Merola and Contributors from the ITER Blanket Integrated.
1 ISFNT-10, Portland, OR, September 12-16, 2011 Overview of the Design and R&D of the ITER Blanket System Presented by A. René Raffray Blanket Section.
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
Managed by UT-Battelle for the Department of Energy Stan Milora, ORNL Director Virtual Laboratory for Technology 20 th ANS Topical Meeting on the Technology.
Alpha Magnetic Spectrometer - 02 Flight Safety Review Phase II May , 2007 Analysis - Welding and Brazing Dan Rybicki – Materials Analysis Jacobs.
Final Meeting TW5-TSW-001 Deliverable 7 SCKCEN, L. OomsCulham, October 23–24, 2006.
EFDA EUROPEAN FUSION DEVELOPMENT AGREEMENT 16th TOFE Madison, Sept , EUROPEAN TECHNOLOGICAL EFFORT IN PREPARATION OF ITER CONSTRUCTION ROBERTO.
W coating of CFC tiles for the JET new wall - Task Agreement: JW6-TA-EP2-ILC-05 Manufacturing and testing of W-coated CFC tiles for installation in JET.
ITER test plan for the solid breeder TBM Presented by P. Calderoni March 3, 2004 UCLA.
NML High Energy Beam Absorbers and Dump 29-August-2011 Beams-doc-3928.
Pacific Northwest National Laboratory U.S. Department of Energy TBM Structure, Materials and Fabrication Collaboration Issues R.J. Kurtz 1, and A.F. Rowcliffe.
Progress to Date PPPL Advisory Board Meeting May 20101NSTX Upgrade – R. L. Strykowsky CD-0 Approved February 2009 The NSTX Upgrade Project organization.
Conceptual Design Requirements for FIRE John A. Schmidt FIRE PVR March 31, 2004.
Pacific Northwest National Laboratory U.S. Department of Energy Initial Cost Estimates for Development of DCLL TBM Ferritic Steel Structural Components.
US Test Blanket Module Partially Integrated Testing Sandia is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for.
Background information of Party(EU)’s R&D on TBM and breeding blankets Compiled and Presented by Alice Ying TBM Costing Kickoff Meeting INL August 10-12,
1 PFC requirements  Basic requirements  Carbon based  Provisions for adding (interface design included in research prep budget)  NBI armor  Trim coil.
Mario Merola EU R&D on Divertor Components Presented by Mario Merola EFDA Close Support Unit, Garching, Germany.
1 A Self-Cooled Lithium Blanket Concept for HAPL I. N. Sviatoslavsky Fusion Technology Institute, University of Wisconsin, Madison, WI With contributions.
Leslie Jones Target Design Engineer Goran Skoro, Steve Lilley, (Stuart Ansell)– Neutronic Dan Wilcox – Engineering Simulation Dan Coates – CAD - TRaM ISIS.
Technology R&D Activities for the ITER full-Tungsten Divertor
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.
Update on the ESS monolith design Rikard Linander Monolith and Handling Group ESS Target Division TAC 10, Lund, Nov 5,
Development of Cryo-Module Test Stand (CMTS) for Fermi Lab (R.L.Suthar, Head,CDM, BARC) Cryo-Module Test stand (CMTS) is a very sophisticated equipment.
First Wall Panel - Overview
Plan on how to work safely with Beryllium
FIP/1-1 Development of Tungsten Monoblock Technology for ITER Full-Tungsten Divertor in Japan 25th Fusion Energy Conference (FEC 2014) Saint Petersburg,
Panda Solenoid Content Interface Box Cold Mass Layout Cooling Lines
Quality assurance for Manufacturing Dressed Cavities for SPS prototype cryomodule C. Parente (HL-LHC Technical Quality Officer) Date:
Strategy for conformity of non-standard cryogenic equipment
DCLL TBM Reference Design
X.R. Wang, M. S. Tillack, S. Malang, F. Najmabadi and the ARIES Team
Produktentwicklung und Maschinenelemente
DCLL Blanket Analysis and Power Core Layout for ARIES-DB
Modified Design of Aries T-Tube Divertor Concept
Welds in the magnet system
Phase II Collimators : design status
Quality Regulation for Mechanical Equipment RESSQ – Mech
Dennis Harwig and Bill Mohr, EWI
Conceptual design of the Cryogenic System of Comprehensive Research Facility for Key Fusion Reactor Core Systems Liangbing Hu Sep.4.
Presentation transcript:

Swiss Industries - 20 th June Divertor and Blanket Systems: Design, Required technologies and Schedule M. Merola Head of the Internal Components Division The views and opinions expressed herein do not necessarily reflect those of the ITER Organization.

Swiss Industries - 20 th June ITER Internal Components Divertor and Blanket directly face the thermonuclear plasma and cover an area of about m 2, respectively. All these removable components are mechanically attached to the Vacuum Vessel or Vessel Ports. Max heat released to the internal components during nominal pulsed operation: ~850 MW Removed by four independent water loops at 4 MPa water pressure, ~70 (inlet), ~120 (outlet) °C Blanket Divertor

Swiss Industries - 20 th June Overview of Material Mass MaterialApplicationMass (ton) Divertor components WArmor material53 CFCArmor material3 Cu and Cu alloyPipes, heat sink, functional material10 SteelStructural parts, pipes430 Ni Al bronzeKnuckle & Nose, pins21 Blanket components BeArmor material10 Cu and Cu alloyPipes, heat sink, functional material85 SteelStructural parts, pipes1400 Ni Al bronzePads, etc.tbc

Swiss Industries - 20 th June Divertor system main functions : Exhaust the major part of the plasma thermal power (including alpha power) Minimize the helium and impurities content in the plasma ITER Divertor

Swiss Industries - 20 th June Cassettes in a circular array held in position by two concentric radial rails. Divertor Cassette Layout

Swiss Industries - 20 th June Divertor System Scope - 54 Divertor assemblies Heat flux elements - 5 Major systems: Cassette Body + Integration Outer Vertical Target Inner Vertical Target Dome Plasma-Facing Comp Tests

Swiss Industries - 20 th June Power Handling HIGH HEAT FLUX COMPONENTS FOSSILE FIRED BOILER WALL (ABB) FISSION REACTOR (PWR) CORE ITER DIVERTOR DESIGN 12/15 mm ID/OD HEAT FLUX - average MW/m 2 - maximum MW/m – 5 10 – 20 Max heat load MJ/m 2 Lifetime years Nr. of full load cycles Neutron damage dpa Materials Ferritic-Martens. steel Zircaloy ~ CuCrZr & CFC/W Coolant - pressure MPa - temperature °C - velocity m/s - leak rate g/s Water-Steam <50 Water <50(SG) Water – – 11 <10 -7 Comparisons

Swiss Industries - 20 th June First Divertor (CFC/W) is well into procurement phase (5 PAs) −PFCs: Last PA signed March Definition of QA for all parties done. Preparation for prototype manufacturing. −HHF Testing facility in RFDA: PA signed March Commissioning planned July −Cassette Body and integration: PA signature 8 th May 2012 Status of Divertor HHF testing of Plasma Facing Units

Swiss Industries - 20 th June All 3 Domestic Agencies have been qualified. CFC Armoured Areas 1000 cycles at 10 MW/m cycles at 20 MW/m 2 W Armoured Areas 1000 cycles at 3 MW/m cycles at 5 MW/m 2 Divertor Qualification Prototypes

Swiss Industries - 20 th June Status of W Technology R&D in EU 2000 cycles at 15 MW/m 2 on W Most of all the W repaired monoblocks behaved like not-repaired ones 200°C, 0.1 and 0.5 dpa in tungsten - Successfully tested up to 18 MW/m 2 Unirradiated cycles x 20 MW/m 2 – no failure

Swiss Industries - 20 th June Blanket System Functions Main functions of ITER Blanket System: Exhaust the majority of the plasma power. Contribute in providing neutron shielding to superconducting coils. Provide limiting surfaces that define the plasma boundary during startup and shutdown.

Swiss Industries - 20 th June Modules 1-6 Modules 7-10 Modules ~1240 – 2000 mm ~850 – 1240 mm Shield Block (semi-permanent) FW Panel (separable) Blanket Module 50% 40% 10% Blanket System

Swiss Industries - 20 th June Design Heat load on blanket Group 1 : 1 – 2 MW/m² Normal heat flux panels Group 2 : 3.5 – 5 MW/m² Enhanced heat flux panels

Swiss Industries - 20 th June First Wall Finger Design SS Back Plate CuCrZr Alloy SS Pipes Be tiles Normal Heat Flux Finger: q’’ = ~ 1-2 MW/m 2 Steel Cooling Pipes HIP’ing Enhanced Heat Flux Finger: q’’ < ~ 5 MW/m 2 Hypervapotron Explosion bonding (SS/CuCrZr) + brazing (Be/CuCrZr)

Swiss Industries - 20 th June –Each DA must demonstrate technical capability prior to start procurement. –2 phase approach: I. Demonstration/validation joining of Be/CuCrZr and SS/CuCrZr joint (done) II. Semi-prototype production/validation of large scale components (on-going) FW Pre-Qualification Requirements 6 Fingers in 1 to 1 scale 2 slopes, 4 facets

Swiss Industries - 20 th June Shield Block Design Slits to reduce EM loads and minimize thermal expansion and bowing Poloidal coolant arrangement. Cut-outs at the back to accommodate many interfaces (Manifold, Attachment, In-Vessel Coils). Basic fabrication method from either a single or multiple-forged steel blocks and includes drilling of holes, welding of cover plates of water headers, and final machining of the interfaces.

Swiss Industries - 20 th June Blanket Manifold A multi-pipe configuration has been chosen, with each pipe feeding one or two BM’s replacing the previous baseline with a large single pipe feeding several BM’s -Higher reliability due to drastic reduction of number of welds and utilization of seamless pipes. -Higher mechanical flexibility of pipes. -Superior leak localization capability due to larger segregation of cooling circuits. -Well established manifold technologies.

Swiss Industries - 20 th June Tolerances General Tolerances described in Standards do NOT always meet our requirements ISO :1989 Tolerances for linear and angular dimensions … ISO :1989 Geometrical tolerances...

Swiss Industries - 20 th June Key Technology Areas Welded structures made of austenitic steels: NG-TIG, EB, Laser, TIG, MIG, … High heat flux joining technologies (Tungsten, Beryllium, CuCrZr): HIP’ing, brazing, casting, EB Heat Flux Testing of actively cooled components Non-destructive Examinations RX, UT, … Piping, flexible supports for pipes Insulating coatings, Low friction coatings, Anti-size coatings Precise machining, metrology High-Vacuum technologies, Pressure Tests, He Leak Tests

Swiss Industries - 20 th June Manufacturing / Welding Qualifications  Qualification of Welding Procedure Specification (WPS) WPS according to EN ISO and EN ISO nn Preliminary WPS is qualified according to EN ISO nn Qualification if quality level B achieved EN ISO 5817 for arc welding EN ISO serie for power Beam welding Welding Procedure Qualification Record (WPQR)  Other equivalent national or international standards and codes may be acceptable subject to the IO’s written approval.  The welding qualification for Quality Class 1 components shall be witnessed by ITER recognized Independent Inspection Authority, e.g. Third Party Inspector.  Welders, operators and NDT personnel shall be qualified (EN 287/ EN1418/ EN 473)

Swiss Industries - 20 th June NDT of welds in Steel Supports N.B. ITER Vacuum Handbook requirement: use of qualified liquid penetrants o Radiographic test for welds (EN 1435) o Ultrasonic Test for welds (EN 22825) o Visual Test for welds (EN 970) o Liquid Penetrant Test for welds (EN 571)  Volumetric examination  Other equivalent national or international standards and codes may be acceptable subject to the IO’s written approval. o Quality level B of EN ISO5817/ EN ISO o ITER Vacuum Handbook Attachment 1: Welding  Surface crack examination  Acceptance Criteria

Swiss Industries - 20 th June Engineering Support Services Design supporting analysis (Electro-Magnetic, thermal, mechanical) Development of component design, including the production of 2D drawings and 3D models. This activity requires the possibility to receive and deliver CAD files in of CATIA_V5 format. Good knowledge and understanding of the codes, standards, and design criteria used in ITER. The work may require the presence of the Contractor’s personnel at the working site of the ITER Organization, for extended periods of time, for the purpose of design review and data gathering.

Swiss Industries - 20 th June Divertor Procurement Schedule 17.P2C.RF Divertor Dome: signed 9 th June P2A.JA Divertor Outer Target: signed 17 th June P2D.RF Divertor Heat Flux Tests: signed 23 rd February P2B.EU Divertor Inner Target: signed 22 nd March P1.EU Divertor Cassette and Integration: signed 8 th May P2E.EU Divertor Rails: September 2014

Swiss Industries - 20 th June Blanket Procurement Schedule 16.P1A.CN/EU/RF Blanket First Wall: November P1B.CN/KO Blanket Shield Block: November P3.RF Blanket Module Connections: July P1A.EU Blanket Manifolds: March 2014

Swiss Industries - 20 th June The ITER plasma facing components are one of the most technically challenging components of the ITER machine An extensive R&D effort has been carried out world-wide to develop suitable high heat flux technologies o Divertor plasma-facing components o Blanket First Wall The ITER Divertor design and R&D has reached a stage of maturity to allow the start of procurement in June 2009 Substantial engineering effort (design and analysis) is planned for the Blanket System in 2012 Key technology areas includes: o Austenitic steel welding (Divertor cassette, Blanket shield block) o Piping (Blanket manifold) o Precise machining of metallic materials (Divertor rails) Summary and Conclusions