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Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.
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Identifying and quantifying a complete set of full-power initiating events during early design stages of high-temperature gas-cooled reactors
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Assessment of Fission Product Release in High-Temperature Gas-Cooled Reactors using TRISO Fuel for Radiological Consequence Assessment
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MELCOR Best Practices for High Temperature Gas-cooled Reactor Modeling.
Abstract not provided.
Modular High Temperature Gas-Cooled Reactor: Severe Accident Phenomena and Safety Criteria [Slides]
Radionuclide Retention within Modular HTGR Fuel
Cooling Channel Optimization in Additively Manufactured Gas Cooled Reactor Core
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Analysis of Graphite Matrix Kinetics and Burnoff Products under Off-Normal High-Temperature Gas-Cooled Reactors Conditions
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Improvement Of The SCALE-XSPROC Capability For High-Temperature Gas-Cooled Reactor Analysis
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High Temperature Gas-cooled Reactors: Core Design
General Attributes of Modular Prismatic and Pebble Bed HTGRs Common features and physics Neutronics Thermal-Fluidics Plant Systems and Power Conversion Instrumentation and Control Normal Operation and Power Maneuvers
Modular High Temperature Gas-Cooled Reactor: Safety Design Approach
Deployment Objectives Flexibly co-locate with new industry users of nuclear energy Steam and electric cogeneration applications Direct process heat with temperature ranges from 700°C to 950°C Enabling Requirements Meet regulatory dose limits at the Exclusion Area Boundary (EAB) 25 rem Total Effective Dose Equivalent (TEDE) for duration of the release from 10 CFR 50.34 (10 CFR 52.79) at Exclusion Area Boundary (EAB) for design basis accidents EAB is estimated approximately 400 meters from the modular HTGR plant (to support co-location with industrial facilities) Meet safety goals for cumulative individual risk for normal and off-normal operation Design goal: meet EPA Protective Action Guides (PAGs) at EAB 1 rem TEDE for sheltering Design basis and beyond design basis events are considered Realistically evaluated at the EAB Emergency planning and protection
Modular High Temperature Gas-cooled Reactor: Accident Analysis
Types of Potential Accidents and Reactor Response Codes and Tools Experimental Validation Safety Analysis Approach Licensing Modernization Project Use of PRA in LMP, ASME/ANS, Non-LWR PRA Standard Methods for Incorporating Passive System Reliability into a PRA
Modular High Temperature Gas-Cooled Reactor: Licensing Part III
Recent Licensing Experience- Advanced and Micro- Reactors Recent Designs Additional Designs Licensing Challenges for advanced reactors Functional Containment Emergency Planning Zones Autonomous and Remote Operation Transportation Manufacturing Licenses NRC License vs. DOE Authorization Siting and Environmental Impact
Modular High Temperature Gas-Cooled Reactor: Licensing Part II
Past US HTGRs and Licensing Approaches
Modular High Temperature Gas-Cooled Reactor: Accident Analysis
Licensing Modernization Project (LMP) Risk Informed Approach Selection of Licensing Basis Events (LBEs) Frequency-Consequence Target LBE Cumulative Risk Targets Structures, Systems, and Components (SSC) Safety Categories Classification Evaluation of Defense in Depth (DID) Use of Probabilistic Risk Assessment (PRA) in LMP Process PRA Policy Statement American Nuclear Society (ANS) Non-Light-Water Reactor (non-LWR) PRA Standard
MELCOR Accident Progression and Source Term Analysis for a Gas-Cooled Reactor.
Abstract not provided.
MELCOR INTEGRATED SEVERE ACCIDENT CODE FOR HIGH TEMPERATURE GAS COOLED REACTOR APPLICATIONS.
Abstract not provided.
Demonstrating Distributed Fiber-Optic Temperature Sensors in a Simulated Gas-Cooled Reactor Outlet
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Progress in the HTTF Benchmark and RELAP5-3D Gas-Cooled Reactor Validation
This slide set presents results of analysis done in the first year after the kickoff of the HTTF benchmark. This work includes the development of a new RELAP5-3D model of the facility and collection and presentation of results from one of the exercises in the benchmark. Highlights include good agreement between the new and legacy models for full-power steady state and similar predictions of maximum block temperature during a pressurized conduction cooldown. Additionally, code-to-code comparisons of a full-power steady state and depressurized conduction cooldown (DCC) from full-power steady state as part of Problem 2 Exercises 1A and 1B show good agreement on temperatures predicted in the core but considerable spread in central reflector temperatures. During the DCC, temperature behavior is similar across all models, but cooldown rates are dictated by the performance of the reactor cavity cooling system