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Removing Safeguards and Security Roadblocks for Advanced Reactors.
Abstract not provided.
A Tool Kit for Generating Simulated Radiation Measurements for Advanced Reactor Safeguards and Security
A tool kit was developed to simulate and analyze passive radiation measurements of molten salt reactor (MSR) operations to support development of nuclear safeguards approaches for this emerging reactor technology. A Transient Simulation Framework of Reconfigurable Modules (TRANSFORM) multiphysics simulation of an MSR produces time-dependent isotopic inventories at user-selected locations within the model. The tool kit implements the Gamma Detector Response and Analysis Software (GADRAS) application programming interface to inject the TRANSFORM isotopic inventories extracted/processed by a Python pipeline into GADRAS models of user-defined geometries. The TRANSFORM inventories are the source terms used to obtain synthetic measurements from GADRAS-defined detectors. The speed of TRANSFORM and GADRAS simulations enables surveying the large design space of MSRs (e.g., fuel type, fuel salt composition, number of loops) and the plethora of measurements (e.g., location, detector type, and collimation) within the reactor. This has enabled timely assessment of the various measurement locations and detectors to identify the most effective and efficient safeguards approach for a specific MSR design. Lastly, the tool kit also simulates extracted samples that can be aged to a desired dose, enabling stakeholders to optimize a measurement plan to use sample analysis as an element within a broader material accountancy plan.
Advanced Reactor Deployment: U.S. Safeguards and Security Challenges.
Abstract not provided.
Advanced Reactor Deployment: Safeguards and Security Challenges.
Abstract not provided.
Sabotage Targets for Advanced Reactors: Focus on Micro-Reactors.
Abstract not provided.
Removing Safeguards and Security Roadblocks for Advanced Reactors.
Abstract not provided.
Evaluating Geologic Disposal Pathways for Advanced Reactor Spent Fuels.
Abstract not provided.
Advanced Reactor Development: Gas-Cooled Reactor First Quarter 2023 Report
ART Program First Quarter report for 2023. Entries for Fuels Development and Qualification, High Temperature Materials Development, Graphite Development and Qualification, and Design Methods Modeling and Validation.
Cross-Cutting Capability in MOOSE for Advanced Reactor Simulation
This presentation highlights NEAMS multiphysics work conducted by the MOOSE team in fiscal year 2022.
CARD: CFD for Advanced Reactor Design
Software Tools and Expertise To Address Multiphase Flow Challenges in<p>Research, Design, and Optimization</p><p>This is the annual CARD project update to be presented at the 2024 FECM/NETL Spring R&D Project Review Meeting.</p>
Methodology and Tool for the Physical Security Analysis of Micro and Advanced Reactors
Powerpoint presentation for INSTAR annual meeting. Data and results are hypothetical and do not represent any actual nuclear plant.
Nuclear Science & Technology. Research and Development to Enable Advanced Reactor Demonstrations and Deployment
Presentation for OT Defender Fellows visit to INL
Accelerating Rare Events Estimation for the Safety Evaluation of Advanced Reactor Technologies
Poster for the LDRD presentation event.