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RENEW THEME IV WORKSHOP. Power Extraction Panel Preliminary Research Thrust Ideas Robust operation of blanket/firstwall and divertor systems at temperatures suitable for efficient power conversion.
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RENEW THEME IV WORKSHOP Power Extraction Panel Preliminary Research Thrust Ideas Robust operation of blanket/firstwall and divertor systems at temperatures suitable for efficient power conversion PANEL MEMBERS:Neil Morley, Charlie Baker, Pattrick Calderoni, Richard Nygren, Arthur Rowcliffe, Mohamed Sawan, Ron Stambaugh, Grady Yoder UCLA, March 2-4, 2009
Greenwald Report on Initiatives • While there are definitely “single-effect” data still needed, don’t limit I-7 to just single-effect science • Focus 1-9 on preparation and execution of partially-integrated, to fully integrated environment/function experiments • Rename I-10 based on the knowledge gap, and not the facility I-7 Engineering and materials physics modeling and experimental validation initiative - a coordinated and comprehensive research program I-9 Component development and testing program - coordinated research and development for multi-effect issues in critical technology areas I-10 Component qualification facility
A Framework for Fusion Nuclear Science and Technology Development Theory/Modeling/Database Design Codes, Predictive Cap. Basic Separate Effects Multiple Interactions Partially Integrated Integrated Component Design Verification & Reliability Data • Fusion Env. Exploration Property Measurement Phenomena Exploration • Concept Screening • Performance Verification Non-Fusion Facilities (non neutron test stands, fission reactors and accelerator-based neutron sources, plasma physics devices) Testing in Fusion Facilities
Suggestions for overarching thrusts and “granular” thrusts Building a fusion nuclear science and technology capability: A coordinated R&D and engineering design program • Single- (especially for LMs) and multiple-effect database • Validated predictive capability sufficient to proceed to design and interpret partially-integrated and integrated experiments • Reestablish FNST human resources, research capability, and expertise • Granular Thrusts Examples: • Fusion relevant thermofluid MHD for PbLi blankets thrust • RAFS, W fabrication methods and characterization thrust • Tritium transport and removal from the PbLi thrust • Chemistry and isotope control in coolant/breeder/purge flow streams • Ceramic breeder unit cell thermomechanics exploration thrust • Integrated modeling platform for multi-effect simulation thrust • Component level engineering design and analysis center • MHD and plasma coupling for liquid surfaces PFCs thrust • …
Suggestions for overarching thrusts and “granular” thrusts Survive and grow in the fusion environment: Fusion break-in experiments for FW/blanket, material, and diagnostics performance • Partially- and fully integrated effects, failure, and reliability database • Validated predictive capability sufficient to proceed to design and interpret moderate fluence, long exposure experiments • Use test stands, fission reactors, plasma devices, ITER TBM (first ~10 years, HH->DT) and FNF initial operation (if available) • Granular Thrusts Examples • Fusion environment tolerant diagnostic capability • Partially-integrated mockup and prototype qualification testing • Virtual TBM: system wide modeling and validation • Prompt and cyclic fully integrated thermomechanical and thermofluid MHD responses • Corrosion and tritium transport in integrated blanket systems (early life) • Functional impact of radiation damage in ceramics (early life) • …
Suggestions for overarching thrusts and “granular” thrusts Feasibly and reliability of the fusion power components: establishing tritium self-sufficiency and continuous high grade power extraction for fusion • Middle-life, fully integrated effect and reliability database • Validated predictive capability sufficient to design first Demo • Requires a new Fusion Nuclear Facility with long pulses, moderate NWL and fluence, and significant testing area and flexibility • Granular Thrusts Examples • Fusion material and component functional response to fusion spectrum irradiation (middle-life) • Multi-module interactions with common support and cooling systems • Validation of the principles of tritium self-sufficiency in complete system • Long pulse current drive and fueling in fusion environment • Failure modes, effects, rates and mean time to repair for random failures and planned outage (all in-vessel components) • Iterative design / test / fail / analyze / improve programs for reliability growth and safety (all in-vessel components) • …