Post-Irradiation Analysis of U-Pu-Zr Fuel Incorporating Am and Np Actinides: Fuel-Cladding Interactions in EBR-II and Advanced Microscopic Examination

Principal Investigator
Name:
Di Chen
Email:
[email protected]
Phone:
(208) 526-6918
Team Members:
Name: Institution: Expertise: Status:
Luca Capriotti Idaho National Laboratory Fast Reactor, Fast Reactor MOX Fuel, Fuel Cladding Chemical Interaction (FCCI), HT9, Irradiated Fuels, Oxide Fuels, PIE Other
Tiankai Yao Idaho National Laboratory Amorphization, Ceramics, Characterization, Corrosion, Environmental Degradation, Grain Growth, High Burnup Fuel, High Density Fuels, Nuclear Fuel, Nuclear Waste, Spark Plasma Sintering, Uranium Compounds Other
Daniele Salvato Idaho National Laboratory EBSD, EDS, FIB, Ion Irradiation, Microstructure, Neutron Irradiation, PIE, SEM, TEM Post Doc
Mukesh Bachhav Idaho National Laboratory APT Other
Di Chen Idaho National Laboratory Cladding, Fuel Other
Experiment Details:
Experiment Title:
Post-Irradiation Analysis of U-Pu-Zr Fuel Incorporating Am and Np Actinides: Fuel-Cladding Interactions in EBR-II and Advanced Microscopic Examination)
Hypothesis:
"Our hypothesis is that these cladding infiltrations are assisted by the high vapor pressures of elements like Am and Sm. Therefore, more extensive examinations are required to more fully quantify the major and minor phases present in the FCCI region." In essence, the research aims to understand the mechanism behind the infiltration of elements like Am (and possibly Sm) into the cladding, suspecting that high vapor pressures of these elements could be the reason for such behavior. The proposal
Work Description:
Sample Details: The subject of this examination is a fuel pin from the X501 experimental assembly. This fuel pin includes minor actinide additions (Am and Np). The specific composition of this experimental fuel pin in the X501 assembly is U-20.2Pu-9.1Zr-1.2Am-1.3Np with HT9 cladding. Objective: Understand the impact of minor actinide integration into metallic fuel systems. Examine post-irradiation effects, particularly interactions between the fuel and its cladding. Explore cladding infiltrations which may be influenced by the high vapor pressures of elements like Am and Sm. Analysis & Findings: Electron microscopy was used for analysis despite challenges posed by high dose rates. Observations include a porous center, Zr distribution, phase decomposition, and several secondary phases/precipitates.A significant feature was the infiltration of Am on the cladding inside wall as a planar front. Methods & Techniques: Sample Preparation: The sample, stored at the Irradiated Materials Characterization Laboratory (IMCL) within the Material Fuel Complex (MFC), will undergo focused ion beam (FIB) activities for preparation. Advanced Microscopy: Transmission Electron Microscopy (TEM): Will carry out sub-micron chemical composition analysis and phase identification. Specifically, TEM diffraction patterns and STEM-EDS will be used for phase identification. TEM provides 2D images with atomic resolution. Atomic Probe Tomography (APT): Offers 3D atomic-scale mappings of elements, delivering detailed compositional details. Instrumentation Schedule: FEI Quanta 3D Focused Ion Beam: 5 days for crafting TEM samples and APT tips. TEM Titan: 4 days for TEM operations. Cameca LEAP 5000X: 5 days for APT examination. Team & Roles: Dr. Di Chen: Principal investigator. Along with Dr. Salvato, will perform FIB & TEM. Dr. Bachhav: Responsible for the APT experiment. Dr. Capriotti and Dr. Yao: Assisting in experimental characterization, overseeing experimental logistics, and contributing to publication. Deliverables: A final report will be submitted to NSUF. Findings will be presented at conferences. Results will be published in journals such as the Journal of the American Ceramic Society, Acta Materialia, or the Journal of Nuclear Materials. All work will be completed within nine months of the award of the project.
Project Summary
In pursuit of understanding the integration of minor actinides in metallic fuel systems, this study delves into a comprehensive post-irradiation analysis of U-Pu-Zr fuel, augmented with Am and Np actinides. Leveraging samples from the X501 experimental assembly with a composition of U-20.2Pu-9.1Zr-1.2Am-1.3Np, the investigation primarily centers around fuel-cladding interactions under irradiation in the EBR-II reactor. Preliminary electron microscopy findings highlighted a porous center, diverse phase decomposition, and secondary precipitates, with a conspicuous infiltration of Am on the cladding's inner wall. Suspecting that such behaviors might be attributed to the high vapor pressures of elements like Am (and potentially Sm), a hypothesis was formed. To further validate or refine this hypothesis, advanced microscopic tools, including Transmission Electron Microscopy (TEM) and Atomic Probe Tomography (APT), are proposed. TEM aims at delivering sub-micron compositional analysis, while APT promises 3D atomic-scale element mappings. The cumulative results from these methodologies will offer profound insights into the implications of minor actinides in metallic nuclear fuels, potentially guiding the design and operation of future reactor systems.
Relevance


The Department of Energy's Office of Nuclear Energy (DOE-NE) is at the forefront of ensuring that nuclear energy remains a reliable and safe source of power, with an emphasis on enhancing its sustainability, efficiency, and safety. Our proposed research on the post-irradiation analysis of U-Pu-Zr fuel enriched with minor actinides directly aligns with this mission, aiming to fortify our understanding of nuclear fuel behaviors under specific conditions.

Advancing DOE-NE's Mission: By delving into the intricacies of fuel-cladding interactions, particularly with the integration of actinides like Am and Np, our research seeks to address the challenges and opportunities pertinent to fuel performance. Such knowledge is pivotal in advancing the DOE-NE's mission of safe and sustainable nuclear energy deployment.

Support for DOE-NE Topics: Our research resonates with specific DOE-NE topics focused on the behavior of advanced nuclear fuels. By employing advanced microscopic tools such as TEM and APT, we are not only adhering to but elevating the standards set for precise investigative methodologies in the realm of nuclear research.

Ties to the Mission & Topics: The outcomes of this study promise practical implications for reactor design and operation, making our research endeavors intimately tied to DOE-NE's primary objectives. Our focus on actinide-enriched fuels bridges the critical knowledge gap, especially given the limited work being done in this specific area.

Addressing Knowledge Gaps: The current landscape of nuclear research reveals a substantial knowledge void when it comes to understanding the behaviors of minor actinides in metallic fuel systems. Our research seeks to fill this gap, providing invaluable insights that have hitherto been unexplored.

Synergies & Mission Need: This project is not an isolated endeavor. It aims to complement and build upon ongoing projects, both direct and competitively funded, thereby ensuring a comprehensive approach to the challenge at hand. Our findings will not only augment the collective knowledge base but also offer practical solutions that address critical mission needs, underscoring the relevance and urgency of our proposed research.

In summation, our research is not just timely but essential, echoing DOE-NE's objectives and addressing the pressing needs of the nuclear energy landscape.