NSUF Awards 33 Rapid Turnaround Experiment Research Proposals

Department of Energy Nuclear Science User Facilities Awards 33 Rapid Turnaround Experiment Research Proposals

 

IDAHO FALLS -- The U.S. Department of Energy (DOE) Nuclear Science User Facilities (NSUF) has selected 33 new Rapid Turnaround Experiment (RTE) projects, totaling up to approximately $1.2 million. These projects will continue to advance the understanding of irradiation effects in nuclear fuels and materials in support of the mission of the DOE Office of Nuclear Energy.

 

NSUF, first established at Idaho National Laboratory (INL), is the nation’s only user facility overseen by the Office of Nuclear Energy. NSUF provides research teams with access to reactor, post-irradiation examination, high-performance computing, and beamline capabilities at a diverse mix of affiliated partner facilities in university, national laboratory, and industry institutions across the country at no cost to the user.

 

NSUF competitively selected the 33 RTE projects from high-quality proposals submitted during the solicitation period. Each proposal was evaluated based on a variety of factors including feasibility, mission relevance, and scientific-technical merit.

 

RTE project research teams include 22 Principal Investigators (PIs) from universities, nine from national laboratories, one from a foreign institution, and one from industry who will work with the NSUF on their proposed experiments. The newly awarded RTE projects are:

PI Name

Institution

Proposal Title

Facility

Assel Aitkaliyeva

University of Florida

Investigation of fuel-cladding chemical interaction (FCCI) in irradiated U-Pu-Zr fuel

Idaho National Laboratory – Materials and Fuels Complex

Bai Cui

University of Nebraska-Lincoln

Irradiation Damage in (Hf0.2Zr0.2Ta0.2Nb0.2Ti0.2)C High-Entropy Ceramics

Center for Advanced Energy Studies Microscopy and Characterization Suite

Ben Maier

University of Wisconsin

in-situ Transmission Electron Microscopy during Ion-Irradiation Studies of Cold Spray Coatings for Accident Tolerant Cladding

Argonne National Laboratory – Intermediate Voltage Electron Microscope Tandem Facility

Brad Baker

United States Naval Academy

Characterization of Radiation Tolerance of Advanced Joining Techniques for Oxide Dispersion Strengthened Steels under Ion Irradiation

Center for Advanced Energy Studies Microscopy and Characterization Suite

Brandon Miller

Idaho National Laboratory

In-situ high temperature Transmission Electron Microscopy (TEM) of radiogenic He in high burnup fast reactor MOX

Idaho National Laboratory – Materials and Fuels Complex

Calvin Parkin

University of Wisconsin

IVEM Investigation of Defect Evolution in Bulk High Entropy Alloys under Single- and Dual-beam Heavy-ion Irradiation

Argonne National Laboratory – Intermediate Voltage Electron Microscope Tandem Facility

Carl Boehlert

Michigan State University

In-situ investigation of the Threshold Incubation Dose for the formation of c-component loops in additively manufactured and powder metallurgy rolled Ti-6Al-4V

Argonne National Laboratory – Intermediate Voltage Electron Microscope Tandem Facility

Christian Deck

General Atomics

Non-destructive X-ray computed tomography analysis of SiC composite tubes neutron-irradiated with and without a high radial heat flux

Oak Ridge National Laboratory – Low Activation Materials Development and Analysis (LAMDA)

Cristian Contescu

Oak Ridge National Laboratory

Micro-structural investigation of the pore structure of uncrept and crept irradiated PCEA graphite specimens with SEM and FIB tomography

Oak Ridge National Laboratory – Low Activation Materials Development and Analysis (LAMDA)

Dalong Zhang

Oak Ridge National Laboratory

In-situ TEM deformation of neutron irradiated FeCrAl alloys

Center for Advanced Energy Studies Microscopy and Characterization Suite

David Carpenter

Massachusetts Institute of Technology

Microstructural characterization of grain boundaries in Hastelloy N corroded in molten FLiBe salt under neutron irradiation

Idaho National Laboratory – Materials and Fuels Complex

David Estrada

Boise State University

Neutron Irradiation and Activation of Fe, Co and Ni Aerosol Jet Printed Structures

Massachusetts Institute of Technology Nuclear Reactor Laboratory

Djamel Kaoumi

North Carolina State University

Correlation between In-situ TEM Observations of Radiation Damage of  an Advanced Ferritic/Martensitic Alloy under Dual-Beam Ion Irradiation and its Mechanical Properties  through In-situ Nanomechanical Testing

Sandia National Laboratory - Tech Area 5 / Ion Beam Analysis Laboratory

Emmanuel Perez

Idaho National Laboratory

Investigation of Ag, Pd, I, Ru, and Sr fission products in bulk and grain boundaries of neutron irradiated SiC

Center for Advanced Energy Studies Microscopy and Characterization Suite

Fabiola Cappia

Idaho National Laboratory

Electron microscopy characterization of fast reactor MOX joint oxyde-gaine (JOG)

Idaho National Laboratory – Materials and Fuels Complex

Gary Was

University of Michigan

Microstructure Analysis of High Dose Neutron Irradiated Alloys

Oak Ridge National Laboratory – Low Activation Materials Development and Analysis (LAMDA)

Jonova Thomas

Purdue University

3D Microstructural Assessment of Irradiated and Control U-10Zr Fuels

Idaho National Laboratory – Materials and Fuels Complex

Julie Tucker

Oregon State University

Synchrotron XRD characterization of long range order in Ni-Cr alloys formed by isothermal aging or irradiation

Brookhaven National Laboratory - NSLS II X-ray Powder Diffraction Beamline

Lance Snead

Stony Brook University

 Determining Annealing Kinetics of SiC to Enable in LWR Accident Modeling

Massachusetts Institute of Technology Nuclear Reactor Laboratory

Leonard Brillson

The Ohio State University

Neutron Irradiation of Ga2O3 to Identify Native Point Defects

Ohio State University - Nuclear Reactor Laboratory

Michael Short

Massachusetts Institute of Technology

 

In situ investigation of the thermomechanical performance of HCP metals and Zircaloy-4 under ion beam irradiation

Sandia National Laboratory - Tech Area 5 / Ion Beam Analysis Laboratory

Philip Edmondson

Oak Ridge National Laboratory

Understanding the local atomic structure in variable composition, irradiated perovskites

Brookhaven National Laboratory - NSLS II X-ray Powder Diffraction Beamline

Qing Su

University of Nebraska-Lincoln

Radiation tolerance of nanostructured amorphous/crystalline SiOC/Fe(Cr) nanocomposites

Texas A&M University ( Ion Beam Laboratory)

Riley Parrish

University of Florida

TEM Characterization of High Burnup MOX Fuel

Idaho National Laboratory – Materials and Fuels Complex

Steven Zinkle

University of Tennessee-Knoxville

 Investigation of neutron irradiation effects on Zr based bulk metallic glass (BMG) via advanced in situ mechanical testing and microstructural analysis

Oak Ridge National Laboratory – Low Activation Materials Development and Analysis (LAMDA)

Takaaki Koyanagi

Oak Ridge National Laboratory

Post-irradiation examinations of SiC composites neutron irradiated at 300°C to 30dpa

Oak Ridge National Laboratory – Low Activation Materials Development and Analysis (LAMDA)

Takuya Yamamoto

University of California-Santa Barbara

APT Characterization of RPV Steels from the UCSB ATR-2 Neutron Irradiation Experiment

Center for Advanced Energy Studies Microscopy and Characterization Suite

Thierry Wiss

European Commission

Grain Size Effects on He and Xe behavior in UO2 and ThO2

Argonne National Laboratory – Intermediate Voltage Electron Microscope Tandem Facility

Tyler Smith

University of Tennessee-Knoxville

Microstructural investigation of hydride reorientation in zirconium based spent nuclear fuel cladding

Oak Ridge National Laboratory – Low Activation Materials Development and Analysis (LAMDA)

Walter Williams

Purdue University

Phase Evolution of Uranium-Zirconium Alloys Under In-Situ TEM Heating

Idaho National Laboratory – Materials and Fuels Complex

Xiang Liu

Idaho National Laboratory

Investigation of the synergistic effects of dual beam irradiation in an austenitic-ferritic duplex alloy

Argonne National Laboratory – Intermediate Voltage Electron Microscope Tandem Facility

Xuan Zhang

Argonne National Laboratory

Investigation of the Tensile-Deformed Microstructure of a Neutron-Irradiated Type 316 Stainless Steel Specimen

Center for Advanced Energy Studies Microscopy and Characterization Suite

Zhenyu Fu

University of Florida

Understand the Fission Products Behavior and Irradiation Effects in UCO Fuel Kernels of Irradiated AGR-1 and AGR-2 TRISO Fuel Particles by Using Atom Probe Tomography

Center for Advanced Energy Studies Microscopy and Characterization Suite