Safety and Risk Assessment for Small Modular Reactors
General slides on INL risk analysis capabilities for SMRs.
22 GENERAL STUDIES OF NUCLEAR REACTORS↗
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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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Securing Solar for the Grid (S2G): SETO Peer Review
In this session at the SETO Peer Review, several solar cybersecurity projects will be discussed. INL will provide an overview of the multi-lab Securing Solar for the Grid (S2G) project. We will highlight the focus areas of standards development and best practices, cybersecurity tool kits and supply chain analysis, and education and workforce development.
14 SOLAR ENERGY↗
First-of-a-Kind Fuel-bearing Molten Chloride Irradiation Experiment
As a dozen MSR developers in the U.S. work toward an aggressive commercialization timeline, many of their fueled-salts—notably, chloride-based compositions—have never been irradiated. Licensing and operating these reactors requires an understanding of (1) the source term, radiation chemistry, and gas generation; (2) unanticipated irradiation-induced corrosion effects; and (3) the impact of burnup on thermophysical properties, all of which can be deduced through irradiation testing. Idaho National Laboratory (INL) is ideally suited to leverage its expertise in chloride salt chemistry, as well as its Neutron Radiography Reactor (NRAD) facility in the Hot Fuels Examination Facility (HFEF) at the Materials and Fuels Complex (MFC), to conduct the world’s first fuel-bearing chloride salt irradiation and fill in the knowledge gaps pertaining to salt chemistry under irradiation. Molten-salt Research Temperature-controlled Irradiation (MRTI) consists of a salt-containing capsule that is internally heated inside of a secondary containment. The experiment must rely on resistive heating to melt the salt before irradiation (to avoid the impact of radiolysis) and once the reactor is turned on and fission reactions commence in the salt, the resistive power can then be reduced. Salt-immersed thermocouples coupled to a controller allow for the heater power to be adjusted as needed to meet experimental objectives. The bulk of the experimental results will be achieved through Post-Irradiation Examination (PIE). At which point a range of different measurements are anticipated to assess the salt/plenum/wall composition, the capsule corrosion rate, and the evolution of salt properties.
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
Release of a High Temperature Engineering Test Reactor (HTTR) Steady-State Multiphysics Model to the Virtual Test Bed
The National Reactor Innovation Center (NRIC) accelerates the demonstration and deployment of advanced nuclear energy through inspiring stakeholders and the public, empowering innovators, and delivering successful outcomes. The Virtual Test Bed (VTB) supports this mission by providing an open-source repository of advanced test reactor models for industry, academia, and the public to utilize. During my time at Idaho National Laboratory (INL), I: • Verified the input files of the High Temperature Engineering Test Reactor • Generated computational results • Created user documentation for the HTTR • Uploaded a steady-state HTTR model to the Virtual Test Bed • Authored a conference publication on the model
22 GENERAL STUDIES OF NUCLEAR REACTORS↗
The Study of Lightbridge Metallic Fuel Rods in MOOSE for Meshing Capabilities and Studying Lightbridge Metallic Fuel Rods with MOOSE
Supporting INL’s mission to transform our nation’s energy future, notably through innovative nuclear energy solutions, this project focuses on modeling accidental tolerant fuel. In collaboration with MIT, we modeled with MOOSE-based tools the Lightbridge metallic fuel design. Lightbridge fuel is envisioned to enable higher power output and larger safety margins for both current and advanced nuclear reactors. We present here the advanced meshing capabilities developed and preliminary physics results.
22 GENERAL STUDIES OF NUCLEAR REACTORS↗
Integrated Energy Systems: Extending Nuclear Energy to Non-Grid Applications
Idaho National Lab is working to improve our energy efficiency around the world through research and implementation of Integrated Energy Systems: Extending Nuclear Energy to Non-Grid Applications. This presentation summarizes the concepts, goals, and actions INL is taking.
08 HYDROGEN↗
First-of-a-Kind Fuel-bearing Molten Chloride Irradiation Experiment
Molten salt reactors (MSRs) have garnered increasing attention recently with several demonstration efforts on the way. A key challenge to the licensing basis for these reactors is the lack of experimental data on fueled salts. This is expected to be crucial to the safety evaluation and licensing basis of reactors of this type deployed in the future. While capability for irradiating molten salts has been reestablished in the recent decade, no enriched fuel irradiation capability has been developed and tested as of yet. A new experiment vehicle under development at Idaho National Laboratory (INL) is presented here. The Molten-salt Research Temperature-controlled Irradiation (MRTI) experiment was developed to host enriched uranium bearing salt samples to be irradiated at a test reactor within the lab complex. One of the key scientific objectives is to provide irradiated salt samples for post-irradiation examination (PIE) to study the impact of fission product generation and neutron/gamma radioactivity on the salt solution and salt-facing wall material. This paper provides a detailed overview of the mechanical design of the experiment, followed by an overview of the fabrication and assembly of an initial prototype vehicle (with non-fuel-bearing salt). A summary of the key analyses conducted as a part of the performance and safety evaluation is then provided. Lastly, an overview of the test conducted in prototypic out-of-pile (non-neutron) environment are shown. These evaluations provide the foundation for a planned irradiation of an enriched uranium-bearing chloride salt sample in the near term. The upcoming irradiation will contain 13 cm3 of UCl3-NaCl salt (93% enrichment) generating around 20 W/cm3 of fission energy during irradiation and a temperature range that can be contained between bounds of 525-900°C.
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
Applying AI/ML Techniques to Nuclear Operating Experience Program and Low-Power Shutdown Initiating Event Study
This is a presentation to the INL AI/ML Activities Workshop in May 2023 discussing the application of AI/ML in nuclear operating experience program and low power shutdown initiating event study.
99 GENERAL AND MISCELLANEOUS↗
Electrical, thermal, and mechanical properties of spatially tailored fiber orientations in 3D printed carbon-carbon composites for EFAS/SPS
Using C-C synthesized at INL from continuous fiber 3D printed preforms, tooling was fabricated, tested, and compared to graphite. The anisotropic properties of the C-C material were leveraged to make stronger and more energy efficient tooling. Future work involves tailoring the fiber orientations to create targeted heating zones and thermal gradients.
36 MATERIALS SCIENCE↗
National Reactor Innovation Center Update
Authorized by the Nuclear Energy Innovation Capabilities Act (NEICA) DOE-Office of Nuclear Energy; INL Nuclear Science & Tech Partner with industry to bridge the gap between research and commercial deployment Leverage national lab expertise and infrastructure
22 GENERAL STUDIES OF NUCLEAR REACTORS↗
Recording of GoToWebinar for Monthly Radiation Chemistry Seminar Series
Recording of GoToWebinar for Monthly Radiation Chemistry Seminar Series. Recording contains slides from INL (previously cleared) and slides belonging to an external invited speaker.
38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEA↗
Conceptual Neutronics Scoping for Ramp Testing in the Advanced Test Reactor
With the closer of the Halden Boiling Water Reactor in 2018, the global capacity for in-reactor power ramp testing has been lost. As such tests provide valuable data for understanding pellet-cladding interaction (PCI) phenomena, finding new facilities for ramp testing is of interest to the United States Accident-Tolerant Fuel (ATF) Program. Several options at Idaho National Laboratory (INL) are being evaluated for adding ramp test capabilities. In the Transient Reactor Test Facility (TREAT), one option is testing inside a Transient Water Irradiation System in TREAT (TWIST) capsule. In the Advanced Test Reactor (ATR), one option under consideration is testing in an I-Loop toward the outer edge of the core. Another is testing in Loop-2A, located in the Center Flux Trap (CFT) of the ATR. In this paper, we examine the conceptual scoping for the Loop-2A experiment known as ATF-2Ramp.
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
Laboratory for Operations and Testing in the United States (LOTUS): NRIC Test Bed
Location: INL Materials and Fuels Complex (MFC); Zero Power Physics Reactor (ZPPR) Facility Purpose: Provides infrastructure to support DOE authorized experiments requiring a Hazards Category 2 facility with an elevated security posture
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
02-21 BWXT
7-year DOE cost-shared ARDP with $24.3M of INL scope Years 1-3: test train design Years 4-5: irradiation Years 5-7: post-irradiation examination (PIE) Irradiation of uranium nitride (UN) tri-structural isotropic (TRISO) prismatic fuel in ATR PIE will be conducted at MFC and ORNL NRIC overseeing program and ensuring continuity between disciplines/steps
22 GENERAL STUDIES OF NUCLEAR REACTORS↗
DOME Test Bed Ecosystem
DOME Ecosystem – Troy Burnett DOME Construction Update – Scott Smith/Brandon Hill Supplemental Shielding Design – Chance Price/ Kyle Reno (Enercon) Polar Crane Status Update – Chance Price Fuel Storage at INL – Todd Sherman DOME User Guide – Marvin Fielding FEEED Overview and Update –Troy Burnett Westinghouse – Erin Orga USNC – Wes Deason Radiant – Elliott Korb
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
Fuel Storage Requirements
2023 No fuel storage plan had been developed 2024 The shipping & receiving requirements are understood A storage location has been selected and designated The storage limitations are known and incorporated The INL coordination & approval groups have been determined
22 GENERAL STUDIES OF NUCLEAR REACTORS↗
Threats to DERs and Tools to Mitigate Them
As the pace of renewable energy development increases, so does the challenge and opportunity to develop innovative solutions to secure renewable technologies. Four national laboratories National Renewable Energy Laboratory, Sandia National Laboratories, Pacific Northwest National Laboratory, and Idaho National Laboratory are working together to increase cybersecurity maturity levels for solar stakeholders. INL will discuss a DER threat briefing and operator tools and training developed under the Securing Solar for the Grid (S2G) project.
14 SOLAR ENERGY↗
Comparison of Error Rate Depending on Operator Expertise and Simulator Complexity
This paper analyzes operator's error rate from experiments, depending on the expertise and simulator complexity. This study uses the Rancor Microworld, a simplified simulator developed by INL, and the Compact Nuclear Simulator (CNS), a less simplified simulator developed by the Korea Atomic Energy Research Institute (KAERI). The error rates were measured from simulation data of a total of 72 participants, and the collected error rate data were analyzed using analysis of variance (ANOVA) test.
99 GENERAL AND MISCELLANEOUS↗