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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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At least 253 records · Page 14
All sourcesNASA NTRSDOE OSTI
DOE OSTI2021

Modeling Interface Debonding in Coated Fuel Particles with BISON

Here we introduce a meshed debonding model intended for use with tristructural isotropic (TRISO) fuel particles. The ability to better examine the potential effects of interface debonding between the coating layers will enable a host of investigations of the stress state when complex loading and interactions between coated fuel particles are taking place. In this work, the debonding model is discussed in detail. Then, simulations are presented to show the capabilities and limitations of the model. First, a traditional high-temperature gas reactor TRISO particle is considered. Then, a TRISO particle in a graphitic matrix is analyzed, followed by a TRISO particle in a silicon carbide matrix.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2016

Constituent Redistribution in U-Zr Metallic Fuel Using the Advanced Fuel Performance Code BISON

Previous work done by Galloway, et. al. on EBR-II ternary (U-Pu-Zr) fuel constituent redistribution yielded accurate simulation data for the limited data sets of Zr redistribution. The data sets included EPMA scans of two different irradiated rods. First, T179, which was irradiated to 1.9 at% burnup, was analyzed. Second, DP16, which was irradiated to 11 at% burnup, was analyzed. One set of parameters that most accurately represented the zirconium profiles for both experiments was determined. Since the binary fuel (U-Zr) has previously been used as the driver fuel for sodium fast reactors (SFR) as well as being the likely driver fuel if a new SFR is constructed, this same process has been initiated on the binary fuel form. From limited binary EPMA scans as well as other fuel characterization techniques, it has been observed that zirconium redistribution also occurs in the binary fuel, albeit at a reduced rate compared to observation in the ternary fuel, as noted by Kim et. al. While the rate of redistribution has been observed to be slower, numerous metallographs of U-Zr fuel show distinct zone formations.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗
DOE OSTI2019

Execution of Targeted Experiments to Inform BISON for ATF Materials: An Advanced Approach to Tube Burst Testing

This report describes a new, advanced experimental approach for testing tube specimens loaded by internal pressure. The approach allows conventional tube burst testing to be performed and employs digital image recording and analysis for conducting noncontact optic strain measurements. Section 1 provides a brief introduction and motivation for the project. Section 2 describes the selected approach and provides technical details regarding the modified experimental tube burst system: a commercial infrared furnace redesigned to support this work by adding two 50-mm- diameter optic ports to make the specimen visible during the burst tests, and a digital camera used to record specimen images, lens, and optic filters. Section 3 briefly analyzes a typical burst test and the digital image correlation dataset, recorded during the experiment, and discusses the experiment outcome including local strains along the tube specimen. Additionally, section 3 focuses on the issues influencing the in situ strain measurement accuracy and final results and suggests changes in the experimental scheme to improve data quality and reliability. The conclusion summarizes the work performed to date and discusses possible future activity.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2019

Modeling the IFR-1 Experiment: A BISON Metallic Fuel Benchmark

As the 1970s nuclear reactor fleet slowly begins the decommission process, the US Department of Energy Office of Nuclear Energy (DOE-NE) aims to stimulate and support the construction and implementation of new nuclear reactors across the country in hopes of continuing the generation of clean, reliable, resilient energy. As a result, various efforts have been introduced to accelerate this process, including the Versatile Test Reactor project (VTR) and the Nuclear Energy Advanced Modeling and Simulation (NEAMS) program.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2023

Blue Bison ATR Advanced CCUS System (Final Report)

The objective of this project was to design a carbon capture system that could be installed on a 220 MMSCFD blue hydrogen (Blue H 2 ) facility (Blue H 2 Plant) utilizing auto-thermal reforming (ATR) technology and identify potential sequestration options for the carbon dioxide (CO 2 ) produced from the Blue H 2 Plant.

08 HYDROGEN↗
DOE OSTI2024

Improvement of mechanistic fuel-cladding chemical interaction modeling in BISON

This report describes work performed during FY2024 under the auspices of the Nuclear Energy Advanced Modeling and Simulation (NEAMS) program to inform and improve mechanistic models of fuel-cladding chemical interaction (FCCI) in metallic fuel. For fuel-side FCCI, atomistic simulations were performed to determine the diffusivity of iron (Fe) in the $\alpha$ and $\gamma$ phases of uranium (U). A model of liquid penetration of cladding due to melting of the fuel-side FCCI region was updated to account for the finite size of the FCCI region, and the model was validated through comparison with tests performed in the Fuel Behavior Test Apparatus (FBTA). For cladding wastage formation, a reduced-order model was improved by comparison with a multi-scale mechanistic model to better quantify the ROM parameters.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2015

Fully-Coupled Metallic Fuel Performance Simulations using BISON

This document is a set of slides intended to accompany a talk at a meeting. The first topic taken up is zirconium redistribution. The rod edge Zr increase is evidently due to the Soret term and temperature gradient. Then metallic fission gas release modeling is considered. Based on a GRSIS/FEAST model, the approach of generating fission gas in the fuel matrix is described. A sensitivity study on parameters is presented, including sodium bond & diffusion coefficient sensitivity along with dt sensitivity. Finally, results of some coupled simulations are shown, with ideas about future work.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗
DOE OSTI2017

Development of a Clad Activation Capability in BISON using ORIGEN

This work describes the ongoing coupling work establishing ORIGEN as a physics module for depletion, activation, and decay in the MOOSE/BISON fuel performance code. The current phase has focused on the implementation of an activation model, mainly intended for evaluation and comparison of accident tolerant cladding designs within a single fuel performance framework. The next phase will develop a capability for fuel depletion. New aspects of this work include: investigation of how to allow the high-fidelity ORIGEN capability to be interoperable extension of existing lower-fidelity cladding models (e.g. based only on fast fluence), introduction of recalculation thresholds to reduce computational cost during multi-physics iterations, and runtime experiments to assess the cost of this additional physics relative to the baseline MOOSE/BISON fuel performance calculations. The current results show activation increases runtime by a factor of approximately 7, but additional optimizations, discussed in the conclusions, are possible.

Wieselquist, William↗