US ITER DCLL TBM Design DCLL TBM ASSESSMENT AND DESIGN TEAM U. of Cali as long as nia, Lo

US ITER DCLL TBM Design DCLL TBM ASSESSMENT AND DESIGN TEAM U. of Cali as long as nia, Lo www.phwiki.com

US ITER DCLL TBM Design DCLL TBM ASSESSMENT AND DESIGN TEAM U. of Cali as long as nia, Lo

O’Mahar, Julie, Managing Editor has reference to this Academic Journal, PHwiki organized this Journal US ITER DCLL TBM Design DCLL TBM ASSESSMENT AND DESIGN TEAM U. of Cali as long as nia, Los Angeles M. Abdou, M. Dagher, S. Smolentsev S. Sharafat, N. Morley, M. Youssef, A. Ying General Atomics C. P.C. Wong, D. Carosella, C. Baxi Consultant S. Malang, A. Rowcliffe, D. Sonn, S. Tourville U. of Wisconsin, Madison M. Sawan, G. Sviatoslavsky Oak Ridge National Laboratory P. Fogarty, Y. Katoh, B. Pint, T. Mann, S. J. Zinkle Idaho National Laboratory B. Merrill Pacific Northwest Laboratory R. J. Kurtz University of Cali as long as nia, San Diego D. K. Sze Lawrence Livermore National Laboratory S. Reyes Los Alamos National Laboratory R. S. Willms S in addition to ia National Laboratory R. Nygren, T. Tanaka, D. Youchison, M. Ulrickson 2006 US-Japan Workshop on Fusion High Power Density Components in addition to System Inn on the Alameda, Santa Fe, New Mexico, USA November 15-17, 2006 Presented by Clement Wong DCLL-TBM PbLi-loop on the transporter He-loops at the TCWS Outline Key features of DCLL blanket concepts Selection of DCLL TBM R&D items as long as DCLL DEMO in addition to HH-TBM Utility of DCLL HH-TBM DCLL HH-TBM in addition to Ancillary Loops Design Development Schedule Key Features of Dual Coolant Lead-Lithium (DCLL) Concepts Helium is used to cool first wall in addition to reduced activation ferritic steel (RAFS) e.g. F82H structure. Helium is also used as long as first wall/blanket preheat in addition to tritium control. Breeder is self-cooled PbLi moving at a slow velocity < 10 cm/s. – allowing high Tout (700°C) leading to th~ 40% (CCGT) Use SiC flow channel inserts (FCI) to: provide electrical in addition to thermal insulation to reduce MHD pressure drop in addition to to decouple high temperature PbLi bulk flow from cooler RAFS structure, also provide higher corrosion resistance temperature with only near stagnant PbLi in contact with the RAFS in the gap EU design, FED, 61-62, 2002 US ARIES ST A design in progress: Community recommendation to focus on RAFS mid-2002 Selected PbLi DCLL blanket as our reference option 12/04 Smaller TBM module recommended by TBWG 5/05 Improved Helium flow from parallel to series between FW in addition to structure 5/06 Adjustment on back plenum design DCLL TBM Colorado College US www.phwiki.com

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DCLL Blanket Has Minimum Critical Issues in addition to Can Become A High Per as long as mance DEMO Blanket Advantages of DCLL Concept No need as long as separate neutron multiplier, like Be or Pb No damage to breeder material by thermal effects in addition to /or irradiation Lower chemically reactive than Li Self-cooled PbLi with velocity~0.1 m/s to enhance Tout, minimize MHD effect Flow channel insert (FCI) as long as MHD in addition to thermal insulation With PbLi Tout @ 700 C, projected CCGT thermal efficiency ~40% as long as DEMO A high per as long as mance design with minimum critical issues With ODFS FW layer, blanket per as long as mance can be enhanced With RAFS DCLL blanket can satisfy all DEMO design requirements: Nuclear per as long as mance, FW helium cooling, Waste disposal, Structural Design Requirements, Safety impacts including LOCA, Power Conversion with CCGT Clear R&D path to DEMO identified Neutron wall loading: 3 MW/m2, FW Surface Loading: 0.55 MW/m2 DCLL Fusion Reactor (DEMO) Blanket Can Achieve High th Power Conversion, “a simple approach” Structural material: RAFS, Tmax@ 550 C, all structure cooled by 8 MPa Helium Breeder material: PbLi, MHD in addition to thermal insulator: SiC flow channel insert (FCI) PbLi Tin/Tout =550/700° C He Tin/Tout =500/650°C CCGT: 3 turbines 6 Compressors @ th=48.7% 40% power from 1, 60% power from 2 combined gross thermal efficiency, th ~ 40% 2. Max. neutron wall loading: 3 MW/m2, max. surface heat flux: 0.55 MW/m2 He Tin/Tout =350/450° C CCGT 1 turbine 2 compressors @ th=26.5% 1. Primary Helium Secondary Helium HX DEMO DCLL Blanket R&D Items are Per as long as mance Related DCLL TBM HH-Module has Few Critical Issues DEMO DCLL Blanket ITER DCLL TBM Ferromagnetic effects of TBM to ITER have been analyzed by ITER: Effects from error fields can be corrected, effects on field line perturbation is small, further assessment is needed. means applicable

Four Phases of DCLL TBM as long as the 1st 10 years in ITER DCLL TBM HH-module can Simulate Selected Mechanical, MHD in addition to First Wall Thermal Effects TBM Modules with similar geometry For DEMO PbLi Temperature is Strongly Dependent on of SiC For DT-module PbLi/RAFS Interface Temperature <470° C T Distribution in PbLi channel at exit as long as DEMO T Distribution in PbLi channel at exit as long as DT DCLL TBM DEMO: B=4 T, NWL=3.75MW/m2, FW heat flux=0.5 MW/m2 PbLi: Tin/Tout=460/700°C, V=0.06m/s h=4000 W/mK =100 S/m is needed DT-module: B=4 T, NWL=0.78 MW/m2, FW heat flux=0.5 MW/m2 PbLi: Tin/Tout=360/470°C, V=0.07m/s h=4000 W/mK FCI thickness=0.005m, gap width=0.002m (Integrated Testing in ITER to Establish Predictive Capability) HH-TBM Design in addition to Ancillary Loops Design HH-TBM design Ancillary Loops design HH-TBM in addition to Ancillary Loops Schedule in addition to Key Dates Summary in addition to Status DCLL TBM Assembly FW Assembly Top Plate Assembly Back Plate Assembly Electric Strap Flexible Support Assembly Helium Inlet/Outlet Pipes PbLi Inlet/Outlet Manifold Assembly TBM Frame DCLL TBM section view DCLL TBM Assembly Exploded View, Major Components FW Assembly Grid Plate Assembly Back Plate & FW distribution Assembly Bottom Plate Top Plate Cover Top Plate Assembly PbLi Outlet Manifold Inner Back Plate Channel Assembly Back Plate Cover Assembly He Inlet Manifold PbLi Inlet Manifold SiC FCI DCLL TBM section view Assembly in addition to SiC FCI SiC components Bottom cross-section U-shape FW Grid in addition to diverter plates Grid in addition to divertor plates parts DCLL TBM section view DCLL TBM Design, PbLi Flow Scheme PbLi Concentric Pipe DCLL TBM Design, He Flow Scheme, Circuits/Passes He Flow Distribution Manifold He inlet Manifold PbLi Flow Channels FW He Channels DCLL TBM Design, He Flow Scheme, Inlet Manifold TBM He flow scheme: Series flow: FW & Bottom Plate to Top Plate to Grid & Divider Plates to Back Plate. First Wall He Flow: Two circuits cross flow, seven passes per circuit, variable number of channels per circuit. He Distribution Manifold FW He Channels He Inlet Manifold He Outlet He Inlet FW counter flow Top plate He distributor to The grid in addition to divider plates DCLL TBM section view He Inlet Manifold Tritium Production Local TBR in the DCLL TBM is only 0.741 because of the small thickness (42.3 cm) Tritium generation rate in the TBM is 2.1x1017 atom/s (1.02x10-6 g/s) during a D-T pulse with 500 MW fusion power For a pulse with 400 s flat top preceded by 100 s linear ramp up to full power in addition to followed by 100 s linear ramp down total tritium generation is 5.1x10-4 g/pulse For the planned 3000 pulses per year the annual tritium production in the TBM is 1.54 g/year Tritium production in the Be PFC is 1.4x10-9 g/s 7x10-7 g/pulse 2.1x10-3 g/year Peak tritium production rate in LiPb is 2.94x10-8 kg/m3s during the D-T pulse DCLL TBM Ancillary Equipment Loops DCLL TBM coolant circuits, Red-dot circuit shows the primary He loop cooling the first wall in addition to all RAFS structures, Blue-dash circuit shows the Pb-Li loop in addition to the Green-dash circuit shows the secondary helium loop. Ancillary Loops Parameters These loops are over-designed in power h in addition to ling, due to earlier larger TBM dimensions in addition to the allowance as long as testing flexibility Design parameters: First wall surface heat flux 0.5 MW/m2 in addition to neutron wall loading @ 0.78 MW/m2, module width x height = 0.645 m x 1.94 m He loops PbLi loop PbLi Loop Schematic Tritium Line Dump Tank Tritium Extraction Sump Pump Tank Cold Trap Unit Expansion Tank Pressure Control Unit PbLi He heat exchanger PbLi loop located on the transporter US TBM PRIMARY AND SECONDARY Helium LOOPS (He loops located in the TCWS Vault) Main design points: He cooled with 35°C water He/H2O HX with Al tubes to prevent T release Water cooling to keep tube T<160° C “U” tubes heat exchanger to reduce thermal stress Sub-systems: Helium pipe network Pressure control unit 170kW electric heater as long as system in addition to FW heat-up Circulator Tritium extraction Helium purification Thermal insulation TCWS Vault DCLL TBM WBS Definition costing was done beginning at the lowest WBS level Definition Primary Helium Loop Details Helium loop design were per as long as med by a GA helium system engineers Including all He-loop equipment, instrumentation, piping in addition to safety systems etc. Assuming that the procurement packages had been supplied to qualified vendors in a competitive world market bidding process. Some are first of a kind equipment. Manufacturing inspection in addition to qualification st in addition to ards used were based on safety grade level Safety valves Safety piping Safety system instrumentation Helium BOP piping Inlet in addition to exhaust Piping to TCWS Helium purge line piping Helium piping thermal insulation etc. Costing details include: Circulator machine assembly Bypass flow system Flow control valves He circulator instrumentation Temperature instrumentation Pressure instrumentation Flow instrumentation DCLL TBM Milestones in addition to Key Dates Preliminary Design Initiated 31 May 2006 Provide Latest Design In as long as mation as long as RPrS Analysis 30 Sept 2006 Preliminary Design Midpoint Review 30 June 2007 Preliminary Design Review 30 June 2008 Select Fabrication Route 31 Dec 2008 Fabrication Bid Package Initiated 31 Aug 2009 Start Safety Classification Procedure as long as Systems Components 31 Oct 2009 Detailed Design Final Design Review 01 Sept 2010 Provide Final Design Specifications to Complete RFS 28 Feb 2011 Title III Design Review - Prototype Fabrication Initiated 30 June 2011 Complete Prototype Fabrication 30 Apr 2012 Final TBM Design Changes 31 Dec 2012 TBM Fabrication Initiated 28 June 2013 Complete TBM Fabrication 30 Apr 2014 Complete TBM Acceptance Tests 30 Jan 2015 TBM ready as long as shipping 31 Mar 2015 (18 months be as long as e ITER 1st plasma) Blue ones are necessary inputs to safety analysis RPrS: Report Preliminary on Safety RFS: Report Final on Safety O'Mahar, Julie Desert Shamrock Managing Editor www.phwiki.com

DCLL blanket concept has been proposed in addition to well-studied by US in addition to EU blanket in addition to reactor design experts US team selected the DCLL TBM after extensive reviews in addition to assessments With RAFS, DCLL blanket concept has the potential to be a high per as long as mance blanket (gross th~40%) as long as DEMO with minimum critical issues Clear R&D paths have been identified as long as DEMO in addition to DCLL TBM, many items are common to the EU HCLL TBM Design DCLL TBM has strong common interest from China in addition to Japan US has unique capabilities to address identified R&D items – RAFS fabrication is under development with inputs from US vendors – SiC composite FCI is the key as long as high thermal in addition to blanket per as long as mance Requirements on SiC composite as long as FCI are much lower than as long as SiC first wall in addition to the development can piggyback on decades of study on SiC as structural material in addition to with input from US vendors – MHD analysis in addition to experiments have made significant progress We are completing the second iteration of the DCLL TBM pre-conceptual design Primary in addition to secondary helium loops in addition to PbLi loop in addition to corresponding components have been identified with well defined WBS structure DCLL TBM is ready to proceed to the preliminary design phase DCLL TBM Design Summary in addition to Status DCLL TBM section view

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