Reports, Studies & Presentations
Providing access to information that advances nuclear energy technologies toward commercialization, while ensuring the continued safe, reliable, and economic operation of the existing nuclear fleet, is at the core of GAIN’s mission.
Reports
2020 – Document-INL/EXT-20-58467 – Report on FY 2020 Testing in Support of the Development and Extension of ASME Code Rules for Grade 91 – Yanli Wang, et al
2022 – Document-INL/RPT-22-70619 – Summary Report of INL Sensors and Instrumentation Activities in SPHERE and MAGNET – Troy Unruh, et al
2023 – Document-INL/RPT-23-71733 – Microreactor Applications in U.S. Markets – Evaluation of State-Level Legal, Regulatory, Economic and Technology Implications – Steve Aumeier, et al
2022 – Document-LA-UR-22-29025 – In-Situ Spatial Mapping of Hydrogen in Yttrium Hydrides at LANSCE – A.M. Long, et al
2022 – Document-LA-UR-22-29612 – Progress Towards a Titanium-Zirconium-Molybdenum Alloy Coreblock Prototype Using Powder Bed Fusion – Michael J. Brand, et al
2022 – Document-LA-UR-22-30557 – Advanced Moderator Material Handbook FY 22 – A.P. Shivprasad, et al
2023 – Document-LA-UR-23-30491 – Advanced Moderator Material Handbook FY23 Version – A.P. Shivprasad, et al
2022 – Document-NEUP-19-17185 – Final Technical Report Demonstrating Autonomous Control Framework Using Graphite Exponential Pile – Bren Phillips, et al
2022 – Document-NEUP-20-19042 – Flexible Siting Criteria and Staff Minimization for Micro-Reactors – Jacopo Buongiorno
2022 – Document-LA-UR-22-30061 – Embedded acoustic sensing and monitoring techniques for small modular reactors – L.B. Beardslee, et al
2023 – Document-LA-UR-23-23350 – Advances in Microreactor Fabrication – Bob Reid, et al
2018 – Document-ORNL/SPR-2018/1071 – Licensing Challenges Associated with Autonomous Control – R.J. Belles, et al
2018 – Document-ORNL/TM-2018/886 – A Survey of Materials for Additive Manufacturing – R.J. Belles, et al
2018 – Document-ORNL/TM-2018/1013 – A Survey of Additive Manufacturing Capabilities – R.J. Belles, et al
2019 – Document-ORNL/TM-2019/1280 – Report on FY19 Testing in Support of Grade 91 Core Block Code Case – Yanli Wang, et al
2019 – Document-ORNL/TM-2019/1305 – Concepts for Autonomous Operation of Microreactors – P. Ramuhali, et al
2022 – Document-INL/RPT-22-68084 – Initial Post Irradiation Examination of Irradiated Yttrium Hydride – M. Nedim Cinbiz, et al
2020 – Document-INL/EXT-20-58163 – Evaluation of Microreactor Inhalation Dose Consequences – Troy P. Reiss
2020 – Document-INL/EXT-20-58467 – Determining the Appropriate Emergency Planning Attributes for Microreactors – Jason Christensen, et al
2020 – Document-INL/EXT-20-59327 – The Elevated-Temperature Cyclic Properties of Alloy 316L Manufactured Using Powder Metallurgy Hot Isostatic Pressing -Ryann Rupp, et al
2020 – Document-INL/EXT-20-59691 – Experience with DireWolf for Heat-Pipe Microreactor Analysis to Support Early Demonstration – Travis Lange
2020 – Document/INL-EXT-20-60441 – DOE Microreactor Program: Summary of Experimental Capabilities Development and Activities – Piyush Sabharwall, et al
2020 – Document-INL/EXT-20-60782 – SPHERE Assembly and Operation Demonstration – Piyush Sabharwall, et al
2021 – Document-INL/EXT-21-61961 – Modeling and Analysis Support for High Temperature Single Heat Pipe Experiment: Current Status and Plan – JunSoo Yoo, et al
2021 – Document-INL/EXT-21-63214 – Global Market Analysis of Microreactors – David Shropshire, et al
2020 – Document-LA-UA-20-23798 – Effects of Heat Pipe Failures in Microreactors – Jack Douglas Galloway, et al
2019 – Document-LA-UR-19-28768 – Microreactor Demonstration and Testing Progress in FY19 – Holly Trellue, et al
2019 – Document-LA-UR-19-29415 – Micro Reactor Instrumentation and Control FY2019 Report – David Mascareñas, et al
2020 – Document-LA-UR-20-20824 – Microreactor Agile Nonnuclear Experimental Testbed Test Plan – Holly Trellue, et al
2022 – Document-LA-UR-20-27683 – Advanced Moderator Material Handbook – A.P. Shivprasad, et al
2022 – Document-LA-UR-22-29969 – Properties of Uranium-Zirconium Hydride Moderated Nuclear Fuel Synthesized by Powder Metallurgy – Caitlin Taylor
Advanced Reactor Supply Chain Assessment, April 2023
High-Assay Low Enriched Uranium Demand and Deployment Options
U.S. Domestic Small Modular Reactor Security by Design
Advanced Reactor Safeguards: Nuclear Material Control and Accounting for Pebble Bed Reactors
Domestic Safeguards Material Control and Accountancy Considerations for Molten Salt Reactors
Evaluation of Optical Techniques for Molten Salt Reactor Materials Control and Accounting
Experimental Validation of Nondestructive Assay Capabilities for Molten Salt Safeguards FY20
GAIN Innovative Materials Research Workshop Summary Report
North Dakota: Trends in State-Level Energy Markets & Policy Report
Wyoming: Trends in State-Level Energy Markets and Policy Report
Transitioning Coal Power Plants to Nuclear Power Report by INL
Investigating Benefits and Challenges of Converting Retiring Coal Plants into Nuclear Plants
Gone with the Steam: How New Nuclear Power Plants Can Re-energize Communities When Coal Plants Close
EPRI’s Repowering Coal-Fired Power Plants For Advanced Nuclear Generation White Paper
Heat Storage Coupled to Generation IV Reactors for Variable Electricity from Baseload Reactors
Trends in State-Level Energy Markets and Policy
Taxonomic Guidance on Advanced Reactors
2022 – Document-ORNL-TM-2022/2619 – Performance of Microreactor Test Article with Embedded Sensors during Testing in the Single Primary Heat Extraction and Removal Emulator – Holden C. Hyer, et al
2019 – Document-ANL-ART-171 – Initial study of notch sensitivity of Grade 91 using mechanisms motivated crystal plasticity finite element method – A. Rovinelli, et al
2020 – Document-ANL-ART-201 – Initial development and verification of a primary load design method based on elastic-perfectly plastic analysis – Mark C. Messner, et al
2020 – Document-ANL-ART-202 – Initial microstructural model for creep-fatigue damage in Grade 91 steel – A. Rovinelli, et al
2020 – Document-ANL-ART-204 – Sample problems for Section III, Division 5 design by inelastic analysis of Grade 91 components – Guosheng Ye, et al
2019 – Document-INL/EXT-19-52614 – Fuel Fabrication Facility Study for FCF HALEU – D.C. Crawford, et al
2019 – Document-INL/EXT-19-53191 – HALEU Decontamination Investigations for EBR-II Recovered Uranium – Michael N. Petterson, et al
2019 – Document-INL/EXT-19-55257 – Key Regulatory Issues in Nuclear Microreactor Transport and Siting – Wayne L. Moe
2020 – Document-INL/EXT-20-57712 – Integration of a Microturbine Power Conversion Unit in MAGNET – Donna Post Guillen, et al
2020 – Document-INL/EXT-20-57821 – Evaluation of Sites for Advanced Reactor Demonstrations at Idaho National Laboratory – Alison Conner, et al
2019 – Document-ANL-ART-165 – Draft ASME Section III Division 5 Code Cases to extend EPP strain limits and creep-fatigue design methods to Grade 91 – M.C. Messner, et al
2019 – Document-ANL-ART-167 – Inelastic analysis procedure based on the Grade 91 unified viscoplastic constitutive model for ASME implementation – M.C. Messner, et al
2022 – Document-INL/RPT-22-66992 – SPHERE Gap Conductance Test – Zachary Sellers, et al
Studies
Molten Salt Reactor Signatures And Modeling Study
Presentations
Trends in State-Level Energy Markets and Policy
Innovative Materials Research Workshop
Welcome Presentation for the GAIN Innovative Materials Research Workshop
Properties of Advanced ODS Alloys and Routes for Application
Accessing the High Damage Regime with Ion Irradiation in the SNAP Program
GAIN Innovative Nuclear Materials Program Overview
Innovative Materials for Advanced Reactor Cladding
Capability Needs for Irradiated and Radioactive Material
Fuel Cladding Materials for the Westinghouse Lead Fast Reactor
Structural and Salt Facing Material Needs Molten Chloride Fast Reactor
Small Modular Reactor Security by Design and Analysis
Performance of DMA Fused Radar and Video
Unique Sabotage Targets for Advanced Reactors
Advanced Reactor Safeguards: Program Overview
Domestic Safeguards & Security Challenges for HALEU
Treatment of Uncertainty in a Risk-Informed Licensing Approach
Advanced Safeguards and Securities Workshop Overview
Technical and Regulatory Considerations for Microreactor NDA Measurements
Pebble Bed Reactors Material Control and Accounting
Material Control Technique Validation for Pebble Fueled Reactors
Machine Learning in Safeguards at Pebble Bed Reactors
Material Control and Accounting in Pebble Bed Reactors
Safeguards Philosophy and Needs
Framework for Microreactor Safeguards and Security
Materials Control & Accounting for Molten Salt Reactors
Molten Salt Reactor Safeguards Modeling
Online Monitoring for Molten Salt Reactor and Matieral Control & Accounting
Flow Enhanced Electrochemical Sensors for Molten Salt Reactors
Experimental Validation of NDA Capabilities for Molten Salt Reactors
Leveraging IAEA Safeguards Experience for US Advanced Reactors
Proliferation Resistance and Physical Protection of GEN-IV Systems
Nuclear Energy Sensors (NES) Website Overview
Advanced Sensor And Instrumentation Program
Integrating Advanced, Real-Time Instrumentation in TREAT Experiments
AGR Instrumentation for Very High-Temperature Gas-Cooled Fuel Experiment
Advanced Reactor Demonstration Facilities
Advanced Reactor Materials Development Roadmap
Probing Nanoscale Damage Gradients in Irradiated Metals Using Nano-Mechanical Test Techniques
NE Microreactor Program Mission and Strategy
Welcome / Importance of Industry Collaboration
DOE-NE Microreactor Program Perspective
Microreactor Program Overview
Systems Integration and Analysis Overview
Microreactor Market Opportunities
Microreactors at Federal Installations
Microreactor Regulatory and Licensing Challenges
Technology Maturation Overview
Material Maturation (Structural Materials / Moderators)
Heat Pipes and Other Heat Transfer Techniques
NEUP Projects Supporting Microreactor Commercialization
NRC Policy and Technical Readiness
EPRI Perspective
Potential Grid Services and Integration Challenges
Microgrid Integration Opportunities
Project Pele Update
Demonstration Capabilities Path Forward and Opportunities
Clean Nuclear Energy for Industry: The Case for SMRs and Microreactors in Puerto Rico
Historical Development of Nuclear Reactor Technology
Structure of NRC Regulatory Framework: Historical Licensing Landmarks
Structure of the Current NRC Regulatory Framework and Considerations for Advanced Technologies
Understanding and Navigating within the Existing Regulatory Framework Webinar Agenda
Understanding and Navigating within the Existing Regulatory Framework Webinar Questions & Responses
Regulatory Considerations When Developing a Deployment Path
What is Regulatory Framework?
Insights on the Efficient Exchange of Licensing Information
Available NRC Licensing Pathways and Associated Hearing Processes
The Use of Non-Public Information in the NRC Licensing Process
Regulatory Condiserations When Developing a Deployment Path
The Impact of the Regulatory Process on Overall Project Risk
Establishing New Routes to Lead the Way to Deployment
Smartly Leveraging Past Work
The Road Less Traveled: Blazing a Trail Customized for Your Vehicle
The Driver’s Seat: Tailoring the Route You Take
Under Construction: Where to Next?
Moderated Panel Discussion with Presenters
GAIN Overview
Overview of the Idaho Operations Office
Nuclear Science & Technology Overview
Energy & Environment Science & Technology Overview
National & Homeland Security Overview
Microreactor Program FY2022
Systems Analysis & Integration Campaign Overview
National Reactor Innovation Center Overview
DOE-NE Cybersecurity R&D
DOE Safety Authorization Process for New Test Reactors
INL Siting Considerations and Electrical Generation
Summary of Contributions to GAIN Innovative Materials Workshop
High-Temperature Gas-Cooled Reactors
Innovative Materials Research Webinar
Advanced Materials & Manufacturing Technologies (AMMT) Program
Characterization of LPBF 316 for Structural Applications in Nuclear
Material Identification and Prioritization
Printed SiC for Nuclear Applications
AM for Strategic Sensor Integration and In Situ Monitoring
Digital Thread for Additive Manufacturing
Standardized Irradiation Testing & Multi-Modal Characterization for Advanced Nuclear Materials
Developments in Physics-Based Modeling and Machine Learning for Environmental Effects in Nuclear Materials
Advanced Materials & Manufacturing Technology: Industry Engagements
Stakeholder Collaboration & Qualification Methodologies
Microreactor Regulatory Development Presentation – August 2020 Workshop
Legacy Fuel Qualification Update – Technology Maturation Panel – August 2020 Workshop
Control Systems – Technology Maturation Panel – August 2020 Workshop
Structural Materials: Progress, Plans, and Priorities – Technology Maturation Panel – August 2020 Workshop
Current Yttrium Hydride Research and Future Plans – Technology Maturation Panel – August 2020 Workshop
NE Microreactor Program Mission and Strategy – August 2020 Wok
Microreactor Applications Research, Validation & Evaluation (MARVEL) Project Presentation – August 2020 Workshop
Non-Nuclear Testing (MAGNET Facility) – August 2020 Workshop
The Case for Microreactors as On-site Generators at Government Installations – August 2020 Workshop
Microreactor Program Overview & Needs Presentation – August 2020 Workshop
Heat Removal and Validation Studies – Technology Maturation Panel – August 2020 Workshop
Instrumentation, Sensors and Controls for MAGNET – Technology Maturation Panel – August 2020 Workshop
Microreactor Research Areas – Developer Panel Session – August 2020 Workshop
Microreactor Research Areas – Developer Panel Session – BWXT Company Overview – August 2020 Workshop
Microreactor Research Areas – Developer Panel Session
Westinghouse eVinci™ Micro Reactor
Micro-Reactor Opportunities and Challenges Presentation – August 2020 Workshop
Microreactor Research Areas – Developer Panel Session – Remote Deployment Challenges
Nuclear Electric Insurance Limited (NEIL) Perspectives presented by Shannon McArdle, NEIL
Perspectives on the Application of Nuclear at Small Scales Presentation – August 2020 Workshop
Project Pele Overview – Mobile Nuclear Power For Future DoD Needs Presentation – August 2020 Workshop
Microreactor Reference Plant Model Presentation – August 2020 Workshop
Investigating Benefits and Challenges of Converting Coal Power Plants to Nuclear Power Plants Presentation by DOE
EPRI Reactor Technology Assessment Guide Presentation
Modular High-Temperature Gas Reactor Technology and Safety Design Approach Presentation
GAIN Nuclear Cybersecurity Intro Webinar – February 2023
Overview of DOE Nuclear Cybersecurity R&D Program Presentation – February 2023
Making Nuclear Portable Presentation – February 2023
OKLO’s GAIN Cybersecurity Webinar Presentation – February 2023
Nuclear Cybersecurity Research Presentation – February 2023
GAIN Update: Coal to Nuclear Transitions Presentation – November 2022
DOE Advanced M&S Program for Fast Reactor Applications Presentation – July 2019
GAIN-NEI Fast Reactor Working Group Workshop Presentation – July 2019
