NSUF Article
Department of Energy Nuclear Science User Facilities Awards 29 Rapid Turnaround Experiment Proposals
IDAHO FALLS -- The U.S. Department of Energy - Office of Nuclear Energy (DOE-NE) Nuclear Science User Facilities (NSUF) has selected 29 new Rapid Turnaround Experiment (RTE) projects, totaling approximately $1.14M. These project awards went to 13 principal investigators from universities, nine from national laboratories, four from industry, and three foreign universities.
The NSUF competitively selected these projects from a pool of high-quality RTE proposals submitted during the solicitation period. Each proposal was evaluated based on a variety of factors including technical approach, mission relevance, and scientific-technical merit.
The NSUF, managed by Idaho National Laboratory (INL), provides unparalleled opportunities for nuclear energy researchers. Through the RTE solicitation, a researcher can apply for no-cost access to NSUF’s capabilities located across the United States. These capabilities encompass irradiation, post-irradiation examination, beamline, and high-performance computing equipment and expertise necessary to advance the understanding of irradiation effects in nuclear fuels and materials in support of DOE-NE’s mission.
The NSUF is currently planning on opening another RTE call this fiscal year. Please stay tuned for more details.
|
Proposer Name |
Institution |
Proposal Title |
NSUF Facilities |
|
Aaron Craft |
Idaho National
Laboratory |
Understanding
Metallic Fuel Relocation Using Neutron Computed Tomography |
Idaho National
Laboratory - Materials and Fuels Complex (MFC) |
|
Benjamin Dacus |
Massachusetts
Institute of Technology |
Microstructural
Evolution in Model & Real RPV steel due to Thermal Aging and Low-Dose
Irradiation using Atom Probe Tomography |
Center for Advanced
Energy Studies - Microscopy and Characterization Suite (MaCS) |
|
Burkan Isgor |
Oregon State
University |
Irradiation of
stainless steel claddings produced by additive manufacturing for in-core
applications |
University of
Wisconsin - Ion Beam Laboratory |
|
Calvin Parkin |
University of
Wisconsin |
IVEM Investigation
of Defect Evolution in FCC Compositionally Complex Alloys under Dual-beam
Heavy-ion Irradiation |
Argonne National
Laboratory – Intermediate Voltage Electron Microscope Tandem Facility (IVEM) |
|
Casey McKinney |
University of
Florida |
Assessing the
Radial Thermal Conductivity Change in FBR MOX Fuel |
Idaho National
Laboratory - Materials and Fuels Complex (MFC) |
|
Charles Hirst |
Massachusetts
Institute of Technology |
Verifying Wigner
energy measurements by in-situ TEM annealing of neutron-irradiated Ti |
Idaho National
Laboratory - Materials and Fuels Complex (MFC) |
|
Cody Dennett |
Idaho National
Laboratory |
Defect generation
and phase stability in single crystal mixed uranium-thorium actinide oxides |
Center for Advanced
Energy Studies - Microscopy and Characterization Suite (MaCS) and University
of Michigan - Michigan Ion Beam Laboratory (MIBL) |
|
Donna Guillen |
Idaho National
Laboratory |
Microstructural Examination
of Irradiation Effects on Metal Matrix Composite Neutron Absorber |
Center for Advanced
Energy Studies - Microscopy and Characterization Suite (MaCS) |
|
Fabio Di Fonzo |
Istituto Italiano
di Tecnologia |
Radiation-induced
Crystallization in Alumina Coatings: Temperature and Yttria Doping Effect. A
Completion Kinetic Study to Model Radiation Resistant Coatings for the Future
Nuclear System. |
Argonne National
Laboratory – Intermediate Voltage Electron Microscope Tandem Facility (IVEM) |
|
Fabiola Cappia |
Idaho National
Laboratory |
Study of minor
actinides redistribution and fission products in high burnup MOX using
Electron Probe Micro Analysis (EPMA) |
Idaho National
Laboratory - Materials and Fuels Complex (MFC) |
|
Francis Garner |
Texas A&M University |
The effects of
stress on void superlattice formation during Cr+ self-ion-irradiation of
chromium |
Center for Advanced
Energy Studies - Microscopy and Characterization Suite (MaCS) and Texas
A&M University - Accelerator Laboratory |
|
Ippei Maruyama |
Nagoya University |
Effect of neutron
radiation on density and mechanical properties of concrete aggregates |
Oak Ridge National
Laboratory - Low Activation Materials Development and Analysis (LAMDA) |
|
Jean Smith |
Electric Power
Research Institute |
Mechanistic Insight
Through TEM Characterization of Intergranular Irradiation-Assisted Stress
Corrosion Crack Tips in As-Irradiated vs. Post-Irradiation Annealed Specimens |
Idaho National
Laboratory - Materials and Fuels Complex (MFC) |
|
Kathleen Goetz |
University of
Tennessee-Knoxville |
Imaging of
Irradiation Effects in Tantalum Alloys for Fast-Spectrum Self-Powered Neutron
Detectors |
Oak Ridge National
Laboratory - Low Activation Materials Development and Analysis (LAMDA) |
|
Michael Miller |
Southwest Research
Institute |
Computational
Thermochemistry of Pathways Toward Synthesis of Uranium Nitride |
Idaho National
Laboratory - Materials and Fuels Complex (MFC) |
|
Michael Moorehead |
University of
Wisconsin |
Heavy Ion
Irradiation and Characterization of Light-Refractory, BCC High-Entropy Alloys |
University of
Wisconsin - Ion Beam Laboratory |
|
Mike Burke |
Electric Power
Research Institute |
In-situ mechanical
testing of neutron-irradiated 304SS exhibiting unusual deformation and
fracture behavior with respect to temperature |
University of
California-Berkeley - Nuclear Materials Laboratory and Westinghouse Churchill
Laboratory Services |
|
Mukesh Bachhav |
Idaho National
Laboratory |
Correlative TEM and
APT approach to elucidate hydride morphology and behavior in ex-service
pressure tube material |
Idaho National
Laboratory - Materials and Fuels Complex (MFC) |
|
Nishant Garg |
University of
Illinois at Urbana-Champaign |
Changes in mechanical
and chemical-structural properties of gamma irradiated calcium silicate
hydrates to an absorbed dose of 189 MGy with respect to pristine samples
subjected to the same temperature history |
Oak Ridge National
Laboratory - Low Activation Materials Development and Analysis (LAMDA) |
|
Pengyuan Xiu |
University of
Michigan |
The sink strength
and radiation parameter effects on microchemical evolution in dual-ion
irradiated additively manufactured and wrought HT9 |
Center for Advanced
Energy Studies - Microscopy and Characterization Suite (MaCS) |
|
Przemyslaw Klups |
University of
Oxford |
Comparison of
Solute Cluster Formation and Evolution in Neutron-Irradiated ATR-2 to
Thermally-Aged Low-Alloy Steels |
Center for Advanced
Energy Studies - Microscopy and Characterization Suite (MaCS) |
|
Rajiv Mishra |
University of North
Texas |
Ion Irradiation and
Examination of Additive Friction Stir Manufactured 316 Stainless Steel
Component |
Center for Advanced
Energy Studies - Microscopy and Characterization Suite (MaCS) and Texas
A&M University - Accelerator Laboratory |
|
Ramprashad
Prabhakaran |
Pacific Northwest
National Laboratory |
Microstructural
characterization of neutron irradiated NF616 (Grade 92) as a function of
doses and temperatures |
Pacific Northwest
National Laboratory - Materials Science and Technology Laboratory |
|
Somayeh Pasebani |
Oregon State
University |
Ion Irradiation and
examination of 304 Stainless Steel and 304 ODS Steel Additively Manufactured
via Selective Laser Melting |
Center for Advanced
Energy Studies - Microscopy and Characterization Suite (MaCS) and Texas
A&M University - Accelerator Laboratory |
|
Stephen Taller |
Oak Ridge National
Laboratory |
The Role of
Precipitate Coherency on Helium Trapping in Additively Manufactured Alloy 718 |
Oak Ridge National
Laboratory - Low Activation Materials Development and Analysis (LAMDA) and
University of Michigan - Michigan Ion Beam Laboratory (MIBL) |
|
Troy Munro |
Brigham Young
University |
Local thermal
properties of fast reactor MOX fuels |
Idaho National
Laboratory - Materials and Fuels Complex (MFC) |
|
Vipul Gupta |
General Electric
Global Research |
Pre-oxidation
effect on ATF cladding performance by characterization of irradiated
FeCrAl-UO2 capsules |
Oak Ridge National
Laboratory - Low Activation Materials Development and Analysis (LAMDA) |
|
Yachun Wang |
Idaho National Laboratory |
A first
Investigation in Lanthanide-induced Grain Boundary Embrittlement in HT9
Cladding via In-situ Micro-tensile Testing |
Idaho National
Laboratory - Materials and Fuels Complex (MFC) |
|
Zachary Mills |
Oak Ridge National
Laboratory |
Coupling CFD and ML
to transform the coated nuclear fuels fabrication process |
Idaho National
Laboratory - Materials and Fuels Complex (MFC) |
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The Nuclear Science User Facilities (NSUF) is the U.S. Department of Energy Office of Nuclear Energy's only designated nuclear energy user facility. Through peer-reviewed proposal processes, the NSUF provides researchers access to neutron, ion, and gamma irradiations, post-irradiation examination and beamline capabilities at Idaho National Laboratory and a diverse mix of university, national laboratory and industry partner institutions.
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