Advanced Reactor Technologies Program Fast Reactor

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ART Program Supports Advanced,Reactor Development,Advanced Reactor Technologies ART. Program supports multiple high level,objectives identified in the 2010 Nuclear. Energy R D Roadmap 2 3,2 Develop improvements in the. affordability of new reactors to enable,nuclear energy to help meet the. Administration s energy security and climate,change goals.
3 Develop sustainable nuclear fuel cycles,overall goal is to have demonstrated the. technologies necessary to allow commercial,deployment of solution s for the sustainable. management of used nuclear fuel that is,safe economic and secure and widely. acceptable to American society by 2050,Advanced Reactor Technologies Program. Program Mission, To research and develop advanced technologies to significantly improve.
the efficiency safety and performance of advanced reactor systems. Advanced Reactor Technologies ART,Fast Reactor Thermal Advanced Advanced Advanced. Technologies Reactor Reactor Reactor Reactor,Technologies Generic Licensing System. Technologies Studies,Advanced Energy ICHMI,Materials Conversion. Structural Materials Are Critical for,Advanced Nuclear Reactor Technologies. Development and qualification of advanced structural materials. are critical to the design and deployment of the advanced. nuclear reactor systems that DOE is developing, High and Very High Temperature Gas Cooled Reactors HTGRs and.
Sodium Cooled Fast Reactors SFRs, Fluoride Salt Cooled High Temperature Reactors FHRs. Structural materials must perform over design lifetimes for. pressure boundaries reactor internals heat transfer. components etc, Performance of metallic alloys and graphite for the long times. and high operating temperatures required is being examined. under the Advanced Reactor Technologies ART Program. ART Program Includes Advanced,Materials R D Activities. Development and qualification of AFR 100,graphite improved high temperature. alloys and ceramic composites for,advanced reactor systems.
Advanced Fast Reactor 100 is an,example of fast reactor systems. Targets local small grids with limited,needs for on site refueling. 250MWt 100MWe sodium cooled core,life 30 years plant life 60 years. AREVA s High Temperature Reactor,is an example of a He cooled system. TRISO fueled graphite moderated,625MWt 315MWe 750 C outlet.
temperature to steam generator plant HTR,life 60 years. Advanced Materials Program Structure,Advanced Materials. Technical Area Lead Sam Sham ORNL,High Temperature Materials. Technical Lead Richard Wright INL,Technical Lead Will Windes INL. Fast Reactor Structural,Technical Lead Sam Sham ORNL.
Active NEUP Projects 16 in High,Temperature Structural Materials. William Corwin DOE NE ART Materials Technology Lead. Project 12 3541 Accelerated irradiations for high dose microstructures in fast reactor alloys University of Michigan. Project 12 3882 Neutron irradiation damage in pure iron and Fe Cr model alloys University of Illinois Urbana Champaign. Project 13 4791 Mechanistic models of creep fatigue crack growth interactions for advanced high temperature reactor components Oregon. State University, Project 13 4900 Corrosion of structural materials for advanced supercritical carbon dioxide Brayton cycle University of Wisconsin Madison. Project 13 4948 Fundamental understanding of creep fatigue interactions in 9Cr 1MoV steel welds Ohio State University. Project 13 5039 Multi resolution testing for creep fatigue damage analysis of Alloy 617 Arizona State University. Project 13 5252 Long term prediction of emissivity of structural material for high temperature reactor systems University of Missouri. Project 14 6346 Integrated computational and experimental study of radiation damage effects in Grade 92 Steel and Alloy 709 University of. Tennessee Knoxville, Project 14 6562 Development of novel functionally graded transition joints for improving the creep strength of dissimilar metal welds in. nuclear applications Lehigh University, Project 14 6762 Microstructural evolution of advanced ferritic martensitic alloys under ion irradiation University of Illinois Urbana. Project 14 6803 Dissimilar joints between 800 H alloy and 2 25 Cr 1 Mo steel Pennsylvania State University. Project 15 8308 Creep and creep fatigue crack growth mechanisms in Alloy 709 North Carolina State University. Project 15 8432 Multi scale experimental study of creep fatigue failure initiation in a 709 Stainless Steel alloy using high resolution digital. image University of Illinois Urbana Champaign, Project 15 8548 Assessment of Aging Degradation Mechanisms of Alloy 709 for Sodium Fast Reactors Colorado School of Mines.
Project 15 8582 Mechanistic and Validated Creep Fatigue Predictions for Alloy 709 from Accelerated Experiments and Simulations North. Carolina State University, Project 15 8623 Characterization of Creep Fatigue Crack Growth in Alloy 709 and Prediction of Service Lives in Nuclear Reactor Components. University of Idaho,Active NEUP Projects in High Temperature. Structural Materials Geographical,Fast Reactor Structural. Activities,Acknowledgments, Lizhen Tan Yuki Yamamoto Mikhail Sokolov Randy Nanstad Phil. Maziasz and supporting staff ORNL,Meimei Li Ken Natesan and supporting staff ANL.
Laura Carroll and supporting staff INL,Advanced Structural Materials Provide. Greater Safety Margin and Design Flexibility,Higher strength for constant. temperature,Reduced commodities,Greater safety margins 200 mm Dia. Longer lifetimes 32 MPa,Higher temperature for constant. Higher plant performance e g,thermal efficiency,Reduced commodities.
Greater safety margins in accident,Combinations of above. Greater design flexibility,Fast Reactor Materials Development and. Code Qualification, Enhanced structural performance of AFR construction materials. would reduce capital costs enable more flexible designs and. increase safety margins,FY 08 FY 09 12 FY 13 15, Established Down selected Intermediate Opt Grade 92 to. advanced one austenitic term testing to complete assessment. materials steel and one support ASME Alloy 709 to initiate. development F M steel Code Code Qualification effort. strategy Qualification and to integrate NEUP,assessment project activities.
Alloy 709 Fe 20Cr,25Ni base austenitic,steel Alloy 709 testing. Grade 92 steel with completed recommended,optimized chemistry for ASME Code Qual. and thermo Opt Grade 92 steel still,mechanical treatment waiting for some longer. term data before,assessment can be made,Optimized Grade 92. Alloy Chemistry, ASTM A1017 11 Grade 92 A182 12a F92 A335 11 P92 A213 11 T92.
C Mn P S Si Cr Mo Ni V Nb B N W Others,Min 0 07 0 3 8 5 0 3 0 15 0 04 0 001 0 03 1 5. Max 0 13 0 6 0 02 0 01 0 5 9 5 0 6 0 4 0 25 0 09 0 006 0 07 2 0 0 02Al 0 01Ti Zr. Carlan et al JNM 2004, Alloy chemistry of optimized Grade 92 is adjusted to. Reduce Ni Si and Mn contents which tend to impair creep. Reduce Cr23C6 type precipitates and increase MX type. precipitates for better high temperature performance. Computational alloy thermodynamics is used to, visualize the effect of alloy chemistry changes on. phase constituents which provide key information,to alloy microstructure and subsequent. thermomechanical treatment process,Optimized Grade 92.
Thermomechanical Treatment TMT, TMT can be easily implemented during conventional Grade 92 production. TMT significantly introducing additional nucleation sites for MX precipitates and. possible refining grain size would noticeably increase material s performance. Creep Resistance, Creep tests have being conducted at 550 600 and 650C and various loads. The longest test has achieved 12 500 h at 550C, The test results indicate noticeable increases in creep strength as. compared to P92 and P91,200 m 200 m 2 m,Creep cavities lots 2 m and a few up to. 10 m formed close to the rupture site of a,Opt Grade 92 specimen tested at 600C.
Advanced Reactor Technologies Program Fast Reactor Structural Materials Sam Sham Materials Science and Technology Division Oak Ridge National Laboratory DOE NE Materials Crosscut Coordination Meeting September 17 2015 ART Program Supports Advanced Reactor Development Advanced Reactor Technologies ART Program supports multiple high level objectives identified in the 2010 Nuclear

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