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Strawman R&D Tasks and R&D Costs. Neil Morley and Alice Ying INL, August 10-12 . US strategy for ITER testing of the DCLL Blanket and First Wall Concept. Develop and deploy a series (~4) of vertical half-port DCLL-TBMs during the period of the first 10 years of ITER operation with
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Strawman R&D Tasks and R&D Costs Neil Morley and Alice Ying INL, August 10-12
US strategy for ITER testing of the DCLL Blanket and First Wall Concept • Develop and deploy a series (~4) of vertical half-port DCLL-TBMs during the period of the first 10 years of ITER operation with • Ferritic steel structure test articles from day one of ITER operation with specific testing goals and diagnostic systems • Associated ancillary equipment systems of various materials • in a transporter behind the bioshield and in space in the TCWS and tritium buildings • using PbLi flow control (bypass/flowrates) to keep temperature of ancillary equipment below material limits (e.g. 475C for PbLi/FS) • Develop international collaboration on PbLi systems to the maximal extent
Electromagnetic/Structural (EM/S) TBM Testing Objectives • Explore/validate general TBM structure and design for later DT operation • Measure forces and the mechanical response of the TBM structure to transient EM loads • Determine ferromagnetic and MHD flow perturbation of ITER fields • Measure thermal and particle load effects on plasma facing surface (Be) and FW structure/heat sink • Establish performance baseline and operational experience of the TBM and basic (He and PbLi flow) ancillary systems • Integration of control systems and diagnostics with ITER systems • Demonstration of required port integration and remote handling procedures • Measurement of thermal time constants and heat loss • Testing heating/filling/draining/remelting and accident response procedures • Perform initial studies of flow effects and Flow Channel Insert performance in steady and transient ITER magnetic field environment • MHD flow distribution and pressure drop in toroidal field and toroidal + poloidal field • FCI performance changes as a function LM exposure time and loading from EM events • Map ITER field in TBM area • Information in the early HH phase can be used: • to modify designs of subsequent TBMs to be deployed in the later DT phase • for ITER DT Licensing.
Key areas and responsible persons for TBM R&D • SiC FCI Development [Katoh] • SiC/PbLi/FS system compatibility [Pint] • Thermofluid MHD [Smolentsev] • Safety R&D [Merrill] • Tritium removal/control systems R&D [Sze/Willms] • TBM Plasma Interface [Ulrickson] • Pebble bed thermomechanics [Ying/Calderoni ] • Structural material and fabrication [Kurtz] • Structural analysis and failure rates [Ghoniem/Sharafat] • Mechanical design [???] • Diagnostics/Instrumentation/Control [???] • Thermofluid Helium systems [Wong ] • Virtual TBM [???] • Mockup facilities [???] • mockup tests [???]
The following information is requested from each responsible person: • Recommended list R&D tasks in your area needed to • Establish basic TBM feasibility • Understand/predict TBM performance • Design and fabricate first TBM – EM/S • Recommended scheduling of listed R&D tasks • Description of each task including: • Main purpose and method (numerical, experimental, …) • Identification of facility/code or description of new/upgraded facility/code required • Description of test section and diagnostics to be fabricated • Anticipated duration and person-years of effort • Any perceived overlap with another US R&D area and similar international R&D
Schedule • cost profile • costing methodologies • Risks • acquisition strategy • Scaling of existing experience (this was what was done for ITER Project Pre-CD0) • Scaling international partner cost estimates on TBM program • Complete bottoms up based on WBS
SiC/PbLi/FS system compatibility [Pint] • Need to establish reference design (materials, operating conditions) asap • Near-term compatibility R&D activities would focus on analysis of existing compatibility for ferritic/martensitic steel with flowing Pb-Li and develop tool for blanket conditions. • Also continue limited number of static capsule tests on candidate piping materials (possibility to avoid coatings or ceramic inserts) • SiC samples to EU for 500C flowing tests • Medium-term activities would be centered on flowing loop experiments • Thermal convection loop • Other loops? • Scoping experiments on stress-corrosion cracking should also be initiated in the near- to medium-term
SiC FCI Development [Katoh] • Initial analysis and strategy development • Confirm if expected cross-sectional distortion is within design allowance. • Develop material design strategy for low flexural modulus and compatibility with other requirements (eg. porous mid-plane) • Develop FCI design strategy that allows longitudinal bending deformation of each face. • Develop method to determine stiffness matrix of relevant materials. • Develop research plan to be able to predict irradiation creep compliance of FCI material. • For electrical (and thermal) insulation: • Establish a reliable technique to measure trans-thickness electrical conductivity of SiC/SiC plates at elevated temperatures. • Identify appropriate method(s) for engineering porous mid-plane components, compensated high resistivity SiC matrix, and insulating SiC-based matrices. Trial-fabricate flat plates of these composites and evaluate baseline properties. • Perform small scale irradiation experiment (rabbit type) on insulating SiC matrix composites. • For mechanical integrity: • Perform detailed evaluation of cross-sectional and longitudinal stress / strain due to thermal gradient. Interact with design people • Design materials / components for low flexural / trans-thickness shear moduli and compatibility with other requirements (eg. porous midplane) • Determine stiffness matrix and other design properties for FCI material. Develop appropriate test methods. • Determine irradiation creep compliance of FCI material. • Perform mock-up (-like) testing to ensure mechanical integrity and sealing are maintained up to design maximum thermal gradient.
Structural material and fabrication [Kurtz]Structural analysis and failure rates [Ghoniem/Sharafat] • Themomechanical heat treatments after fab, hip, weldSpecial emphasis will be needed for specific manufacturing processes and joining techniques such as HIPped and difusion bonded materials (presently not nuclear qualified). • Pre-service Nondestructive inspection • High temperature design rules • Selection of an appropriate ferritic steel (F82H, Eurofer, other?). This is not trivial since the U.S. will need to take advantage of databases developed in Japan and the EU. • Development of joining technology of Be to ferritic steel. (overlap) • Effects of radiation to ~3 dpa at 100-550°C on the deformation and fracture properties of structural materials. • The planned U.S./Japan 15J/16J HFIR irradiation experiment provides a good approximation of the TBM irradiation conditions (300/400°C, 2.5-5 dpa) • Creep-fatigue interaction due to the high number of short operational pulses in ITER • Iteration with Structural Analysis Tasks/Design/Materials and Fabrication
Thermofluid MHD [Smolentsev] • Effectiveness of the FCI as electric/thermal insulator • Flow effects on corrosion rate and thermal stresses in the FCI*(coupled) • Pressure equalization on both sides of the FCI • EM forces in and around the FCI during the disruptions* • 3-D flow effects on the FCI and the whole TBM functions • 3-D MHD pressure drop of flow elements an flow balancing – normal and faulted conditions • Multi-channel flow effect • Design and optimization of the inlet Pb-17Li manifold • Coaxial pipe vs. two separate pipes • Thermal behavior of the TBM during the ITER cycle?* (coupled) • Effect of natural convection, turbulence, etc. on the thermal behavior of the TBM
Safety R&D [Merrill] • Tritium permeation through cooling system pipes • Inventory analysis based on tritium extraction technique • Hydrogen generation – PbLi spray experiment contact mode characterization
Tritium removal/control systems R&D [Sze/Willms] • Fundamental R&D on Tritium extraction technologies for high temperature (coupled) • Permeators Nb, Ta, Pd • Direct contact • Tritium permeation ??? what to be done (coupled to saftey)
TBM Plasma Interface [Ulrickson] • Joining Be and FS (coupled)
Thermofluid Helium systems [Wong ] • Headers and non-isothermal flow distribution • Heat transfer coefficients
Virtual TBM [???] • Morley, Merrill, Sharafat, Smolentsev