ITER Test Blanket Module and the Need for Coordination Outline What ITER means for the World Technology / Chamber / Blanket Community ITER Plans for TBM.

Slides:



Advertisements
Similar presentations
1 Summary Slides on FNST Top-level Technical Issues and on FNSF objectives, requirements and R&D Presented at FNST Meeting, UCLA August 18-20, 2009 Mohamed.
Advertisements

Technical Strategies for Pressure Drop Reduction in LM Blankets N. B. Morley, S. Smolentsev, B. Pint, D.-K. Sze, S. Malang APEX/TBM Meeting February 23,
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.
Presented by: S. Suzuki, Blanket Engineering Lab., Japan Atomic Energy Research Institute, JAERI Contents 1.Outline of blanket development in JAERI 2.Design.
US TBM Activities Update 1- Quick background 2- Recent Activities Mohamed Abdou FNST Meeting held at UCLA, August 2-4,
First Wall Thermal Hydraulics Analysis El-Sayed Mogahed Fusion Technology Institute The University of Wisconsin With input from S. Malang, M. Sawan, I.
US ITER TBM DCLL TBM Design, Analysis and Development C. Wong, M. Dagher, S. Smolentsev and S. Malang FNS/TBM Meeting UCLA, September 19-20, 2007.
Suggested US Plans and Strategy for ITER Test Blanket Mohamed Abdou Presented at APEX/TBM Meeting, UCLA, November 3-5, 2003.
Summary of Current Test Plan for US DCLL TBM in ITER Neil Morley and the US TBM Participants INL, August
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.
US DEMO MS FW / Blanket Assessment Blanket Design Concepts Prepared by Paul Fogarty, Siegfried Malang Mo Dagher With contributions from the US MS DEMO.
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.
Multiple effects for HT DCLL Presented by Neil Morley University of California, Los Angeles US-EU DCLL Workshop November 14-15, 2014 Slides from my colleagues.
A design for the DCLL inboard blanket S. Smolentsev, M. Abdou, M. Dagher - UCLA S. Malang – Consultant, Germany 2d EU-US DCLL Workshop University of California,
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.
Role of ITER in Fusion Development Farrokh Najmabadi University of California, San Diego, La Jolla, CA FPA Annual Meeting September 27-28, 2006 Washington,
Thermofluid MHD issues for liquid breeder blankets and first walls Neil B. Morley and Sergey Smolentsev MAE Dept., UCLA APEX/TBM Meeting November 3, 2003.
The effect of the orientations of pebble bed in Indian HCSB Module Paritosh Chaudhuri Institute for Plasma Research Gandhinagar, INDIA CBBI-16, Sept.
Material System Design Studies of High Temperature Gas-Cooled Solid Breeder Blanket Module A.Hasegawa (Tohoku Univ.) A.Shimizu, T.Yokomine (Kyushu Univ.)
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.
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.
Strawman R&D Tasks and R&D Costs Neil Morley and Alice Ying INL, August
1 Recent Progress in Helium-Cooled Ceramic Breeder (HCCB) Blanket Module R&D and Design Analysis Ying, Alice With contributions from M. Narula, H. Zhang,
1 Test Blanket Module (TBM) Briefing to DOE/OFES and US ITER Project Management Mohamed Abdou Video Conference, September 9, 2004 ITER Program.
Briefings to the Materials Community on ITER Test Blanket Module (TBM) Mohamed Abdou August 11, 2003 Outline 1.What is going on with ITER and TBWG 2.Other.
MHD Modeling and Experiments at UCLA for the ITER Test Blanket Program N. Morley, M. Abdou, A. Ying, S. Smolentsev, M-J. Ni, T. Sketchley, J. Burris, M.
1 Mohamed Abdou With input from M. Sawan (UW), D. Sze (UCSD), N. Morley (UCLA), C. Wong (GA), S. Willms (LANL), A.Ying (UCLA), R. Nygren (SNL), P. Fogarty.
Fusion Science and Technology Mohamed Abdou, Neil Morley, Alice Ying Mechanical and Aerospace Engineering Dept. CESTAR: Center for Energy Science and Technology.
1 U.S. Presentation in TBWG-16 Beijing, China November 15 – 17, Overview of R&D, Time Schedule, and Cost Estimation M. Abdou (25 min.) 2.Possible.
1 VLT Research Highlights ITER Test Blanket Module (TBM) M. Abdou and the ITER-TBM Team Outline 1.Introduction and TBWG activities 2.Technical planning.
ITER test plan for the solid breeder TBM Presented by P. Calderoni March 3, 2004 UCLA.
Overview of UCLA Research Activities on Fusion Nuclear Science and Technology Briefing to Professor Osamu Motojima and Japanese delegation from NIFS and.
Tritium Extraction from a DCLL Blanket Prepared by: Scott Willms (LANL) Collaborators: Brad Merrill (INL), Siegfried Malang (Consultant), Clement Wong.
Conference Call, June 23, 2005 Remarks on US Costing Activities for the US ITER-TBM Mohamed Abdou.
Pacific Northwest National Laboratory U.S. Department of Energy TBM Structure, Materials and Fabrication Collaboration Issues R.J. Kurtz 1, and A.F. Rowcliffe.
Fusion Energy Sciences Program Department of Energy Perspective February 23, E xcellent S cience in S upport of A ttractive.
Charles C. Baker Virtual Laboratory for Technology presented at the U.S. ITER Forum University of Maryland, College Park May 8, 2003 US ITER Technology.
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,
Introductory Remarks to APEX/TBM* Meeting November 3-5, 2003 Mohamed Abdou *ITER Test Blanket Module.
Materials Integration by Fission Reactor Irradiation and Essential Basic Studies for Overall Evaluation Presented by N.Yoshida and K.Abe At the J-US Meeting,
DCLL ½ port Test Blanket Module thermal-hydraulic analysis Presented by P. Calderoni March 3, 2004 UCLA.
Various Strategies for DCLL in the US Technology Program Poor ITER utilization (Lowest Cost Scenario) - Support EU HCLL effort, no independent DCLL TBM.
Review of Thermofluid / MHD activities for DCLL Sergey Smolentsev & US TBM Thermofluid/MHD Group 2006 US-Japan Workshop on FUSION HIGH POWER DENSITY COMPONENTS.
December 13, 2006 Blanket and Shield Design Considerations for Magnetic Intervention G. Sviatoslavsky, I.N. Sviatoslavsky, M. Sawan (UW), A.R. Raffray.
Some slides on UCLA LM-MHD capabilities and Preliminary Incompressible LM Jet Simulations in Muon Collider Fields Neil Morley and Manmeet Narula Fusion.
UCLA - March 8, 2006 US TBM Cost Estimate Status March 8, 2006 Tom Mann.
DCLL Thermofluid/MHD R&D Sergey Smolentsev, Neil Morley and the ITER- TBM thermofluid group US ITER-TBM Meeting August 10-12, 2005 INEL.
1 Discussion with Drs. Kwon and Cho UCLA-NFRC Collaboration Mohamed Abdou March 27, 2006.
Overview of the US ITER Test Blanket Module (TBM) Technical Plan
Material System Thermomechanics Interactions (cont’d) International Collaboration: Role / Impact / Recognition - Serves a unique role in IEA program on.
Highlights of US ITER TBM Technical Plan and Cost Estimates (and Impact of International Collaboration) Mohamed Abdou and the U.S. Team TBWG-17 Presented.
“Report on TBWG Meeting” Mohamed Abdou Presented at APEX / ITER-TBM Meeting November 3 – 5, 2003 UCLA, Los Angeles, CA TBWG-11 Meeting at Garching, Germany,
US Participation in the
Overview of Fusion Blanket R&D In Japan
Material Issues for the US ITER-TBM Program
DCLL TBM Reference Design
Can We achieve the TBR Needed in FNF?
Chamber Technology (CT) and Why Now? General Atomics, San Diego
“Report on TBWG Meeting”
VLT Meeting, Washington DC, August 25, 2005
Remarks on US Costing Activities for the US ITER-TBM
Introductory Remarks to APEX/TBM* Meeting November 3-5, 2003
Mohamed A. Abdou Summary, Approach and Strategy (M. Abdou)
Presented at the ITER TBM Meeting, February 23-25, 2004, at UCLA
Nuclear Analyses for two “Look-alike” HCPB Blanket Sub-modules for Testing in ITER Mahmoud Z Youssef UCLA Presented at ITER-TBM4 Meeting, UCLA, March 2-4,
University of California, San Diego
TITAN - Flow Control and Thermofluid Modeling Tasks
DCLL Nuclear Analysis WBS Costing Mohamed Sawan University of Wisconsin-Madison Mahmoud Youssef University of California-Los Angeles ITER TBM Meeting.
Presentation transcript:

ITER Test Blanket Module and the Need for Coordination Outline What ITER means for the World Technology / Chamber / Blanket Community ITER Plans for TBM and Schedule and Timing of R&D US-Japan Collaboration on TBM General Suggestions for US-Japanese Universities and JUPITER-II Mohamed Abdou Presented at the JUPITER-II Special Meeting at UCLA June 10, 2003

New Momentum for ITER will dramatically impact all World Fusion Programs What happened Impact Technology / Blanket Programs New momentum for ITER: US and China joining ITER, serious negotiations for construction, etc. Budget outlook is alarming: budget cuts to fusion programs in US, Japan, Europe, Russia The world is likely to proceed with ITER with tight budgets Expected Impact: ITER becomes the highest priority; everything else is lower priority. There are not enough funds to do other things!! Will likely be the most impacted Must find ways to be a serious participant in ITER

ITER Plans for Construction and the Role of Chamber / Blanket Technology What is being negotiated for construction are basically 85 packages for various components (poloidal magnets, toroidal magnets, neutral beams, rf, buildings, power supplies, etc.) There is a package for the shielding blanket / vacuum vessel - Not a breeding blanket - R&D is more “industrial”-type - Meaningful R&D roles for Universities and Labs only in limited area (mostly nuclear analysis) There is nothing in the procurement packages or negotiations so far on Breeding Blankets The Breeding Blanket is handled only in the ITER Test Blanket Module (TBM) Program. It is handled through ITER TBWG (Test Blanket Working Group) which has representatives from the Parties and the ITER Joint Central Team

What is the ITER Test Blanket Module Program? The ITER Basic Device has shielding, but no breeding blanket Breeding Blankets will be tested in ITER, starting on Day One, by inserting Test Blanket Modules (TBM) into specially designed ports Each TBM will have their own dedicated systems for tritium recovery and processing, heat extraction, etc. Each TBM will also need new diagnostics for the nuclear-electromagnetic environment Each ITER Party is allocated limited space for testing two TBM’s ITER’s construction plan includes specifications for TBM’s because of impacts on space, vacuum vessel, remote maintenance, ancillary equipment, safety, availability, etc.

ITER Operational Plan Calls for Testing Breeding Blankets from Day 1 of Operation H-Plasma Phase D Phase First DT plasma phase Accumulated fluence = 0.09 MWa/m 2 Blanket Test

ITER First Plasma EU schedule for Helium-Cooled Pebble Bed TBM (1 of 4 TBMs Planned) a final decision on blanket test modules selection by 2005 in order to initiate design, fabrication and out-of-pile testing (Reference: S. Malang, L.V. Boccaccini, ANNEX 2, "EFDA Technology Workprogramme 2002 Field: Tritium Breeding and Materials 2002 activities- Task Area: Breeding Blanket (HCPB), Sep. 2000) TBM Roll Back from ITER 1st Plasma Shows CT R&D must be accelerated now for TBM Selection in 2005

ITER Test Program US-Japan Collaboration Questions 1) If each party is only allowed to test two blanket concepts: a) What are the two favored concepts in Japan? And in US? b) What are the mechanisms in the US and in Japan to arrive at these decisions? c) Should we have joint study/assessments to try to arrive at common concepts to maximize the utilization of limited resources/budgets in both countries? 2) Should the US have collaboration with JAERI separate from collaboration with Japanese Universities? a) How do we enhance US-JAERI collaboration? b) Should we orient JUPITER-II to serve collaboration between US and Japanese Universities on ITER BTM?

ITER Test Program US-Japan Collaboration Blanket Options for ITER Blanket Test Module (BTM) 1) Solid Breeder Blankets – Common Interest in EU, Japan, and US – Collaboration between US and JAERI – Some limited activity under JUPITER-II (Task 2.2) 2) Molten Salt Self-Cooled Concept – Some activity under JUPITER-II – Is it a candidate for ITER TBM? 3) Liquid Metal Blanket Concepts – Self-cooled Li/V concept – Helium-cooled Pb-17Li concept – Helium-cooled Pb-17Li concept with SiC insert (Ferritic Steel is the Reference DEMO material worldwide)

Suggestions for JUPITER-II for Discussion 1. Joint Study to select a liquid breeder option 2. Expand Task 2-2 (Thermomechanics) to include both SiC and ferritic; also include temperature control - with focus on special issues - involve the broader community (blanket, material, safety, PFC, etc.) - find ways for JAERI and EU to provide input (participate?) 3. Modify and Expand Thermofluid Task a) Initiate MHD experiments (in MTOR) and modeling (using newly developed 3-D HIMAG code) on MHD insulators and crack tolerance. b) For MHD flibe: reduce magnetic field consistent with ITER TBM needs, or defer magnet installation for one year.

MTOR experiment design should proceed next year as part of the ITER TBM study. ITER TBM development will require LM-MHD tests of several different kinds in an upgraded MTOR facility  Pressure drop and flow distribution experiments on complex geometry elements such as manifolds, interconnected channels and gradient magnetic fields  Pressure drop, velocity profile and heat transfer in channels with simulated insulator coating imperfections MTOR can accommodate large test structures elongated along the field direction (like manifolds) that are difficult to fit into standard gap magnets.

Coupling of the HIMAG LM-MHD modeling will be invaluable to TBM R&D effort HIMAG is expressly designed to handle: Complex geometries Resolution of small features (boundary layers and cracks) Multiple materials and free surfaces Sample unstructured meshes used in tokamak sector free surface flow simulation, and closed channel simulations resolving a crack of width units in a unit square

ITER relevant heat transfer experiments with Flibe simulants in FLIHY facility  Using our large stainless pipe heat transfer test section already in place it will be possible to simulate ITER TBM FW parameters in both Ha and Re using a reduced field of about T  We can produce longitudinal field of this magnitude (simulating toroidal TBM FW coolant paths) with commercially available water cooled welding cable that we wrap up ourselves.  We can produce transverse field using the same cable wrapped on a different form, or permanent magnets  This idea would use the existing KOH capability and existing power supply in the lab now, with a reduced cost magnet

Similarity of FLIHY large diameter test section with ITER parameters ITER with Flibe at 500 C FLIHY with 20% KOH at 30 C B 5 T0.25 T FW Tube Diameter 1 cm9 cm FW Tube Flow Velocity 8 m/s0.13 m/s L/D Hartmann Number5-10 Reynolds Number11000 Prandtl Number /(1+250*Ha 2 /Re) {Sze} 62% (38% degradation) 1–1.2*Ha 2 /Re {Blums} 99.7% (0.3% degradation)