Community Outreach Webinar at ANS November 13, 2018
FY19 Presentation Slides Winter ANS Community Outreach
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The videos are in playlist format. Use the menu on the upper-left hand side of the video player to select the correct presentation.â
FY19 Workscope Specific Q&A
Consolidated Innovative Nuclear Research FOA Overview
Aaron Gravelle, DOE-ID; John Gilligan, NCSU; JoAnne Hanners, DOE-ID; Gregory Bala, NEUP Integration Office
Scholarship & Fellowship Soliciation Overview
Won Yoon, DOE-NE
NSUF-1 and NSUF-2 Overview
Dan Ogden, NSUF - Idaho National Laboratory
Infrastructure FOA Overview
Jonathan Kirkham, NSUF - Idaho National Laboratory
RC-3: Liquid Metal-Cooled Fast Reactor Technology Development and Demonstration to Support Deployment
Tom Sowinski, DOE-NE
3:30p-4:00p
RC-5: Experimental Validation of High Temperature Gas Reactor (HTGR) Simulations
RC-6: Floride Salt-Cooled High Temperature Reactor (FHR)
RC-6.1: Used FHR Pebble Fuel Storage and Handling
RC-6.2: Experimental Validation of Passive Decay Heat Removal Technology
Diana Li, DOE-NE
4:00p-5:00p
RC-7: Molten Salt Reactor Technologies
RC-7.1: Fuel Salt Sampling Technology Development
RC-7.2: Evaluation fo 316SS Lifetime in MSRs
RC-7.3: Radiation Hardened Vision Systems
RC-7.4: Molten Salt Mechanical Filters
RC-7.5: Shut Off Valve Technology Development
Brian Robinson, DOE-NE
RC-8: Plant Modernization R&D Pathway
RC- 8.1: Digital Instrumentation and Control Qualification
RC-8.2: Analytics to Support Equipment Condition Monitoring
RC-9: Risk-Informed Systems Analysis R&D Pathway
RC-9.1: Use of Integtated PRA and Mechanistic Tools to Accelerate Deployment of Advanced Technologies to LWRs
RC-9.2: Risk-Informed Asset Life Cycle Management and Maintenane Optimization
RC-10: Materials Research Pathway
RC-10.1: Rapid, Multi-Modal Characterization of Concrete's Degradation Tolerance in Support of Second License Renewals of Nuclear Power Plants
RC-10.2: Modeling of Helium Bubble Development During Welding of Irradiated Metal Alloys
Alison Hahn, DOE-NE
NEET-1: Advanced Methods for Manufacturing
NSUF- 1.2: Irradiated Testing of Materials Produced by Innovative Manufacturing Techniques
Tansel Selekler, DOE-NE
FC-4: Used Nuclear Fuel Disposition
FC-4.1: Used Nuclear Fuel Disposition: Disposal
FC-4.2: Used Nuclear Fuel Disposition: Storage and Transportation
John Orchard, DOE-NE
FC-5: Fabrication Process Assessments for Cost Algorithm
FC-6: Interface Tools for Transmutation Data Library
BP Singh, DOE-NE
2:00-2:30p
MS-RC-1: Special Purpose Reactors R&D
Becky Onuschak, DOE-NE
2:30p-3:00p
MS-FC-1: Maintaining and Buliding Upon the Halden Legacy (In-Situ Diagnostics)
Ken Kellar, DOE-NE
3:00p-4:00p
NEAMS-2: Separate Effects Irradiation Testing for Validation of Microstructural Models in Marmot
IRP-NEAMS-1: Extended NEAMS Tools to Support the Development of the Versaltile Test Reactor (VTR) Experimental Program
MS-NE-1: Integral Benchmark Evaluations
MS-NE-2: Nuclear Data Needs for Nuclear Energy Applications
Dan Funk, DOE-NE
4:00p-4:30p
RC-1: Innovative New Nickel Alloys for Molten Salt Reactor Structural Applications
Sue Lesica, DOE-NE
4:30-5:00p
NE-1: Nuclear Energy-Cybersecurity Research Topics and Metrics Analyses
Trevor Cook, DOE-NE
NE-2: Hybrid Energy Systems Design and Modeling
NE-2.1: Studies of Component/System Degradation
NE-2.2: Cyber-Informed System Design
NE-2.3: Systems Control
Martha Shields, DOE-NE
NEET-2: Advanced Ditital Monitoring and Control Technology
NEET-2.1: State of the Art I&C Technologies
NEET 2.2: Advanced Online Monitoring and Diagnostics Technologies
NEET 2.3: Advanced Sensors and Communication
NEET-3: Digital/Electronic Nuclear Field Support Technology
NSUF 1.1: Testing of Advanced Materials for Advanced Sensors for Nuclear Applications
Suibel Schuppner, DOE-NE
RC-2: Salt Behavior in Molten Salt Reactors
RC-2.1: Understanding, Predicting, and Optimizing the Physical Properties, Structure, and Dynamics of Molten Salt
RC-2.2: Understanding the Structure and Speciation of Molten Salt at the Atomic and Molecular Scale
Stephen Kung, DOE-NE
FC-1: Material Recovery and Waste Form Development
FC-1.1: Electrochemical Separations
FC-1.2: Materials Recovery
FC-1.3: Waste Forms Development and Off-Gas Capture
FC-1.3a: Advanced Waste Form Design, Processing, and Testing
FC-1.3b: Iodine Capture From Highly Oxidizing Off-Gas Streams
Patricia Paviet, DOE-NE
FC-3: Advanced Data Integration for Domestic Nuclear SafeguardsMike Reim, DOE-NE
FC-2: Advanced Fuels
FC-2.1: Post Irradiation Examination (PIE)/Non-Destructive Examination (NDE) Techniques for Corrosion Thickness Measurements on ATF Claddings (Coated-Zr, FeCrAl, SiC)
FC-2.2: Studies on Accident Tolerant Control Rods and Core ComponentsFrank Goldner, DOE-NE
FC-2.3: Investigations Iinto Non-Traditional Solid Fuels for Advanced non-Light Water Reactors
FC-2.4: Advanced Creep Testing of Ferritic Steels for Reactor Cladding Applications
FC-2.5: Separate Effects Testing in TREAT using Standard Test Capsules
Janelle Eddins and Ken Kellar, DOE-NE
IRP-NE-1: International Challenge Problem for Nuclear Energy
Janelle Eddins, DOE-NE
RC-4: HTGR TRISO Fuel particle Materials
RC-4.1: Thermomechanical Properties of TRISO Fuel Coating Layers
RC-4.2: Effect of Neutron Irradiation on Fission Product Transport Through TRISO Particle Silicon Carbide Coating Layer
Madeline Feltus, DOE-NE
