Department of Energy Nuclear Science User Facilities Awards 37 Rapid Turnaround Experiment Research Proposals

IDAHO FALLS -- The U.S. Department of Energy - Office of Nuclear Energy (DOE-NE) Nuclear Science User Facilities (NSUF) has selected 37 new Rapid Turnaround Experiment (RTE) projects, totaling approximately $1.6 million. These project awards went to principal investigators from 26 U.S. universities, eight national laboratories, two British universities, and one Canadian laboratory.

 

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.

 

Pi Name

 Institution

Proposal Title

Facility

Ajantiwalay, Tanvi

University of Florida

In-situ nanomechanical characterization of neutron-irradiated HT-9 steel

Sandia National Laboratory - Tech Area 5/Ion Beam Analysis Laboratory (TA-V/IBA) and Idaho National Laboratory - Materials and Fuels Complex (MFC)

Arivu, Maalavan

Missouri University of Science and Technology

Alleviating irradiation-induced precipitation in a Fe-21Cr-5Al alloy via nanostructuring.

Center for Advanced Energy Studies - Microscopy and Characterization Suite (MaCS) and Texas A&M University - Ion Beam Laboratory (IBL)

Ayanoglu, Muhammet

Pennsylvania State University

The microstructure characterization of 21Cr32Ni model austenitic alloy irradiated at BOR60 reactor

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

Bai, Xianming

Virginia Polytechnic Institute

In situ TEM observation of microstructural evolution of sodium-ion battery materials under ion irradiation

Argonne National Laboratory – Intermediate Voltage Electron Microscope Tandem Facility (IVEM)

Cinbiz, Mahmut

Oak Ridge National Laboratory

Scanning/Transmission Electron Microscopy Characterization of Irradiated Zr-1Nb-O During Thermal Treatments

Idaho National Laboratory - Materials and Fuels Complex (MFC)

Davis, Thomas

University of Oxford

Nanoscale analysis of Mn-Si-Ni phase in neutron irradiated T91 at 320C

Center for Advanced Energy Studies - Microscopy and Characterization Suite (MaCS) and Idaho National Laboratory - Materials and Fuels Complex (MFC)

Figueroa, Alejandro

Purdue University

High-burnup U-Mo pore morphology analysis as a function of fission density and rate

Idaho National Laboratory - Materials and Fuels Complex (MFC)

Finkeldei, Sarah

University of California-Irvine

EPMA and TEM Characterization of a UO2 fuel pellet and cladding interaction layer

Idaho National Laboratory - Materials and Fuels Complex (MFC)

Frazer, David

Los Alamos National Laboratory

Elevated Temperature In-situ Scanning Electron Microscopy Microcantilever Testing of U3Si2

University of California - Berkeley - Nuclear Materials Laboratory (NML)

Fu, Zhenyu

University of Florida

Understand the atomic positions of the metallic fission product in UCO Fuel Kernels and Determine the exact stoichiometry of UC, UO phase of Irradiated TRISO Fuel Particles by Using Titan Themis 200 with EELS characterization Capability

Idaho National Laboratory - Materials and Fuels Complex (MFC)

Hawari, Ayman

North Carolina State University

Neutron powder diffraction and transmission in graphite to assess impact of microstructure on neutron thermalization

North Carolina State University - Nuclear Reactor Program (NRP)

Kaoumi, Djamel

North Carolina State University

Correlation of In-situ TEM Characterization and Ex-situ Microchemistry Analysis of Radiation Damage in Metal/Oxide Multilayers

Argonne National Laboratory – Intermediate Voltage Electron Microscope Tandem Facility (IVEM)

Kearney, Sarah

University of Sheffield

Characterization of alpha irradiated and control cementitious grouts / grout components used for nuclear waste encapsulation

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

Kocevski, Vancho

University of South Carolina

Density Functional Theory Study of Defects, Solubility of Fission Products and Pu, and Phase Separation in U3Si2 Nuclear Fuel

Idaho National Laboratory - Materials and Fuels Complex (HPC)

Krogstad, Jessica

University of Illinois at Urbana-Champaign

Radiation Tolerance of Nanoporous Gadolinium Titanate

Argonne National Laboratory – Intermediate Voltage Electron Microscope Tandem Facility (IVEM)

Lenling, Mia

University of Wisconsin

Atom Probe Tomography (APT) Investigation of Radiation Stability of Oxide Nanoclusters in Oxide Dispersion Strengthened (ODS) Steel Manufactured by the Cold Spray Process

Center for Advanced Energy Studies - Microscopy and Characterization Suite (MaCS)

li, wenjing

Canadian Nuclear Laboratories

BET and TEM characterization of nuclear graphite irradiated at temperatures below 230°C

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

Massey, Caleb

University of Tennessee-Knoxville

Nano-precipitate Stability and a'-Precipitation in ODS and Wrought FeCrAl Alloys

Center for Advanced Energy Studies - Microscopy and Characterization Suite (MaCS)

Meher, Subhashish

Idaho National Laboratory

Microstructural characterization of in-situ ion irradiated SiC layer of TRISO fuel

Idaho National Laboratory - Materials and Fuels Complex (MFC) and Sandia National Laboratory - Tech Area 5/Ion Beam Analysis Laboratory (TA-V/IBA)

Patki, Priyam

Purdue University

Role of Irradiation Damage Cascade Descriptors on ODS and Model ODS Nanocluster Evolution

Argonne National Laboratory – Intermediate Voltage Electron Microscope Tandem Facility (IVEM)

Ray, Biswajit

University of Alabama

In-situ investigation of irradiation damage on non-volatile memory

Sandia National Laboratory - Tech Area 5/Ion Beam Analysis Laboratory (TA-V/IBA)

Shao, Lin

Texas A&M University

Irradiation response and mechanical properties of Cr coated Zircaloy-4

Idaho National Laboratory - Materials and Fuels Complex (MFC) and Texas A&M University - Ion Beam Laboratory (IBL)

Short, Michael

Massachusetts Institute of Technology

In situ observation of helium out-gassing mechanism in percolating 1D/2D nanodispersoids for advanced reactor structural material and fuel cladding

Argonne National Laboratory – Intermediate Voltage Electron Microscope Tandem Facility (IVEM)

Smith, Charlyne

University of Florida

The impact of grain orientation on the nucleation of fission gas bubbles in U-Mo fuel

Idaho National Laboratory - Materials and Fuels Complex (MFC)

Song, Miao

University of Michigan

Effect of Irradiation on Nuclear Graphite Microstructure in Relation to Oxidation in Oxygen Environments

Center for Advanced Energy Studies - Microscopy and Characterization Suite (MaCS) and University of Michigan - Michigan Ion Beam Laboratory (MIBL)

Stubbins, James

University of Illinois at Urbana-Champaign

Microstructure characterization of neutron-irradiated Fe-Cr-C model alloys

Center for Advanced Energy Studies - Microscopy and Characterization Suite (MaCS) and Idaho National Laboratory - Materials and Fuels Complex (MFC)

Swenson, Matthew

University of Idaho

Temperature shift evaluation for G-phase nanocluster evolution in ferritic/martensitic alloys

Center for Advanced Energy Studies - Microscopy and Characterization Suite (MaCS) and University of Michigan - Michigan Ion Beam Laboratory (MIBL)

Tang, Ming

Los Alamos National Laboratory

Radiation Stability Study on Nuclear Waste Materials

Argonne National Laboratory – Intermediate Voltage Electron Microscope Tandem Facility (IVEM)

Wang, Yachun

Rensselaer Polytechnic Institute

TEM Characterization of Neutron Irradiated Nd2Zr2O7 and Its Thermal Recovery Behavior

Idaho National Laboratory - Materials and Fuels Complex (MFC)

Wharry, Janelle

Purdue University

Influence of Grain Boundary RIS on Dislocation Mobility in Irradiated Steels

Center for Advanced Energy Studies - Microscopy and Characterization Suite (MaCS)

Yao, Tiankai

Idaho National Laboratory

Irradiation and TEM Characterization of induced Defects in a-U and d-UZr2+x Crystals

Idaho National Laboratory - Materials and Fuels Complex (MFC) and Texas A&M University - Ion Beam Laboratory (IBL)

Zaluzec, Nestor

Argonne National Laboratory

A study using stoichiometry to control structural disorder and subsequent radiation tolerance of rare-earth based zirconates and titanates

Argonne National Laboratory – Intermediate Voltage Electron Microscope Tandem Facility (IVEM)

Zhang, Xuan

Argonne National Laboratory

In-situ TEM Study of the Irradiation Response of Pre-deformed Alloy 709

Argonne National Laboratory – Intermediate Voltage Electron Microscope Tandem Facility (IVEM)

Zhao, Ji-Cheng

The Ohio State University

APT Study of Zr-(Mo, Nb, Ta) Diffusion for Designing the Diffusion Barrier Interlayer of Cr Coated Zircaloy Accident-Tolerant Fuels

Center for Advanced Energy Studies - Microscopy and Characterization Suite (MaCS)

Zheng, Guiqiu

Massachusetts Institute of Technology

Microstructural characterizations of in-core molten salt irradiated TRISO particles

Idaho National Laboratory - Materials and Fuels Complex (MFC)

Zhong, Weicheng

Oak Ridge National Laboratory

Atom Probe Tomography Investigation on the Precipitation of Neutron-Irradiated Alloy 800H/800H-TMP

Center for Advanced Energy Studies - Microscopy and Characterization Suite (MaCS)

Zhou, Weiyue

Massachusetts Institute of Technology

Investigation of the mechanism behind irradiation-decelerated corrosion of Ni-20Cr in molten fluoride salt

Idaho National Laboratory - Materials and Fuels Complex (MFC)