TRU BISON Simulation Overview
The BISON fuel performance code has been used to model minor actinide (MA) bearing metallic ternary fuel. This presentation gives an overview on the progress made so far on this effort, focusing on the modeling of EBR-II experiment X501-G591. Comparisons with PIE have also been made.
Margin to Onset of Nucleate boiling and Flow Instability Studies for Preliminary MITR Design-Demonstration Element Thermal-Hydraulics
This study covers the onset of flow instability (OFI) preliminary results obtained from leveraging correlations, in addition to the preliminary thermal hydraulics results such as pressure, flow velocity, temperature, and oxide layer over the design demonstration experiment (DDE) for the Massachusetts Institute of Technology Reactor (MITR). Current computational fluid dynamics (CFD) models in fluid structure […]
Status Report on Fast Flux Test Facility Mechanistic Fuel Failure Experiment Analysis with BISON for Post Irradiation Examination Support
The renewed interest in metallic U-Zr nuclear fuel alloy has led to a drive for deeper understanding of the mechanisms driving the phenomena observed under irradiation conditions. The Department of Energy Advanced Fuel Campaign has developed infrastructure to support metallic fuel development, including Post Irradiation Examination (PIE) of legacy Fast Flux Test Facility (FFTF) Mechanistic […]
Comparative Post-Irradiation Examination of High Burnup U-19Pu-10Zr: Assessing Prototypic Irradiation Conditions Against Historical and Modeled Fuel Behavior
The development of next-generation sodium-cooled fast reactors necessitates comprehensive research on metallic fuels to maximize economic performance while ensuring safe operation. In this study, we investigated the steady-state irradiation behavior of two high burnup U-19Pu-10Zr fuel pins, DP-36 and DP-40, in preparation for planned safety testing. Post-irradiation examination (PIE) was performed to quantify fuel column […]
An Integrated Approach to Examining Fuel-Cladding Chemical Interaction in U-10Zr Metallic Fast Reactor Fuels: Coupling Machine Learning with Electron Microscopy and Local Mechanical Properties Analysis
Metallic U-Zr nuclear fuel alloy has regained interest as a promising candidate for next generation sodium-cooled fast reactors. Recent studies and technology assessments have identified several areas where improvements, enhanced knowledge, and reliable data are needed to bolster the U-Zr fuel design basis for qualification and commercial use. One of the most constraining phenomena affecting […]
Development of a Thermal Creep Model for Aluminum Alloy 6061 Cladding in U-10Mo Monolithic Fuel Plates
Plate-type fuel elements consisting of a high-density, low-enriched uranium (LEU) U–10Mo-based fuel foil encapsulated in an aluminum alloy (AA) cladding are fabricated using the hot isostatic pressing (HIP) technique. During the HIP process, the fuel plate system is heated to 560 degree celsius, then cooled to room temperature. This heat cycle significantly affects the mechanical […]
Comparison of FAST Experiments to BISON Simulations
The Fission Accelerated Steady-State Test (FAST) experiments utilize the effects of scaling to accelerate the burnup experienced by the fuel. This experimental technique offers a unique opportunity to evaluate the effects of scaling on fuel and cladding material modelling. Currently, models used in the BISON fuel performance code for metallic fuel performance are calibrated for […]
Assessing High Burnup U-19Pu-10Zr Fuel Performance against Historical and Modeled Behavior
Advancing the deployment of sodium-cooled fast reactors (SFRs) requires thorough testing of metallic fuel pins under accident conditions to establish safe operational limits of high burnup fuel. To conduct transient testing, a comprehensive understanding of steady-state fuel behavior obtained through both experimental characterization and accurate predictive capabilities is needed. This study comparatively assesses the steady-state […]
Evaluation of Irradiation Creep Effects in HT9 Cladding for FAST Experiments
The push for advanced reactor fuels for improved reactor safety and efficiency had led to a renewed interest in metallic fuel for nuclear reactor applications. Experimental investigation is necessary to ensure a robust understanding of the thermomechanical properties of new metallic fuel designs. Unfortunately, with the current experimental facilities, thoroughly investigating the responses of metallic […]