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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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This is a status update and description of major post-irradiation examination activities under the DOE's AGR TRISO fuel program. This presentation will be given at the annual program review hosted by INL the week of July 15.
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Microgrid presentation to MARVEL design team
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The domestic and international consensus standards for nuclear criticality safety (NCS) were developed as the lessons-learned from process criticality accidents. These consensus standards were developed to reduce the rate of process criticality accidents in facilities that process, store, handle or transport fissionable materials by hand. After a significant increase in criticality accidents through the mid-1960’s, the rate of criticality accidents decreased due to these standards and the criticality accident rate is extremely low from an industrial safety perspective.
NRAD is a 250-kilowatt TRIGA research reactor that first went online at INL in 1977. (TRIGA stands for Training, Research, Isotopes, General Atomics.) Historically, NRAD was utilized as a neutron radiography reactor that provides comprehensive, non-destructive information about the internal condition of irradiated nuclear fuel. Idaho National Laboratory (INL) has multiple nuclear fuels research and development programs that routinely evaluate irradiated fuels using neutron radiography at NRAD. In recent years, NRAD has gone through a transformation from the single purpose radiography reactor for which it was designed into a multipurpose research reactor, and expanding its in-core irradiation capabilities to support a broader mission for the US Department of Energy (DOE) Nuclear Energy (NE) programs, Basic Energy Science (BES) Programs, as well as Fusion Energy programs. NRAD is a designated user facility under the DOE Nuclear Science User Facility (NSUF) program, and is available for access for general public via a competitive proposal process. More information about NSUF and NRAD are available from the website: https://nsuf.inl.gov/Home/Facility/654.
Presentation detailing work package to develop comprehensive fusion device safety models over the course of the next three years, including references to a blanket, divertor and magnet design, and statistical reliability models
This presentations summarizes the international collaboration work that is occurring in the Advanced Reactor Technologies - Gas-Cooled Reactor (ART-GCR) program. It is part of the 2025 ART-GCR annual review meeting.
This presentation summarizes the work occurring in the Advanced Reactor Technologies - Gas-Cooled Reactor Program. It is part of the 2025 ART-GCR annual program review.
Pronghorn is an engineering-scale, coarse-mesh, thermal-hydraulics tool for supporting reactor-core simulations of advanced nuclear reactors. Most of the current efforts in Pronghorn have been devoted in developing porous finite-volume capabilities and adapting closure correlations for coarse-mesh thermal-hydraulics modeling. However, for liquid-metal reactors (LMRs) with wire-wrapped fuel pin assemblies, a pin-level thermal-hydraulic resolution is required for most safety case studies (pin rupture, channel blockage, etc.). For this purpose, a new Subchannel application is developed in MOOSE, which affords the required flow field resolution, while still preserving an engineering-scale approach. This new solver can be natively coupled to Pronghorn and other MOOSE objects to enable full-core, multi-physics, multi-scale engineering studies. This presentation presents the main features of the SCM code and demonstrates a validation case based on the EBR-II SHRT tests.
Clean Cities and Communities is a U.S. Department of Energy (DOE) partnership that fosters collaboration and innovation to advance transportation energy choices nationwide. More than 75 DOE-designated Clean Cities and Communities coalitions work in urban, suburban, and rural areas to deliver objective technical expertise based on a unique understanding of local markets. As partners with DOE's Transportation Technologies Office, coalitions build bridges between national priorities and local needs to create transportation energy systems that are affordable, reliable, and secure.
Slides for a talk about space nuclear capabilities in modeling and simulation at INL.
Introduction to the Technology Maturation technical area session for the AMMT program review.
Introducing following HRA topics to visitors from Naval Nuclear Labs. - Dynamic HRA Method and Software (LWRS) - HRA Data Collection (LWRS) - HRA Consultation (KINS) - HRA for Advanced Nuclear Reactors (Hobby) - HRA for Non-Nuclear Industries (BEES)
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