NSUF Article

DOE Awards 31 RTE Proposals, Opens FY-20 1st Call

Tuesday, September 17, 2019 - Calls and Awards, Announcement

Projects total $1.1 million; Next proposals due 10/31: Awards will go to 22 principal investigators from universities, six from national laboratories, and three from foreign universities.

IDAHO FALLS -- The U.S. Department of Energy - Office of Nuclear Energy (DOE-NE) Nuclear Science User Facilities (NSUF) has selected 31 new Rapid Turnaround Experiment (RTE) projects, totaling approximately $1.1 million. These project awards went to 22 principal investigators from universities, six from national laboratories, and three foreign universities. The FY 2020 first call is also now open for proposals. More information is available on the RTE page on nsuf.inl.gov.

 

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.

 

Proposer Name

Institution

Proposal Title

NSUF Facility

Al-Amin Ahmed Simon

Boise State University

Performance and Structural Damage Analysis of Chalcogenide Glass Phase Change Temperature Sensors Under Ion Irradiation

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

Alejandro  Figueroa

Purdue University

Multi-Modal Serial Sectioning and Synchrotron Micro-Computed Tomography Analysis of High Burnup Nuclear Fuels

Idaho National Laboratory - Materials and Fuels Complex (MFC)

Andres Morell-Pacheco

Texas A&M University

The influence of proton irradiation damage on the corrosion of Hastelloy N exposed to FliNaK molten salt   

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

Andrew Hoffman

Missouri University of Science and Technology

Advanced microstructural characterization of irradiation-induced phase transformation in 304 steel

Idaho National Laboratory - Materials and Fuels Complex (MFC)

Casey McKinney

University of Florida

Three-Dimensional Characterization of the Grey Phase in FBR MOX Fuel

Idaho National Laboratory - Materials and Fuels Complex (MFC)

Dong Liu

University of Bristol

Investigation of buffer densification using TRISO particles irradiated in PYCASSO project

Idaho National Laboratory - Materials and Fuels Complex (MFC)

Emilie Siochi

NASA Langley Research Center

New Proposal:  Irradiation of Structural Carbon Nanotubes for Nuclear Thermal Propulsion Application

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

Emmanuelle Marquis

University of Michigan

New Proposal: Microstructure analysis of neutron irradiated Alloy 625

Center for Advanced Energy Studies - Microscopy and Characterization Suite (MaCS) and Los Alamos National Laboratory - Plutonium surface Science Laboratory

Fabio Di Fonzo

Istituto Italiano di Tecnologia

Alumina-stabilized coatings under irradiations: towards future generation nuclear systems

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

Gyuchul Park

Purdue University

Effects of cold rolling and induction casting on the phase decomposition and distribution of fission gas bubbles in U-10wt.%Mo alloys at low fluences.

Idaho National Laboratory - Materials and Fuels Complex (MFC)

Hwasung Yeom

University of Wisconsin

Microstructural Investigation of Radiation Stability of Cold Spray Manufactured Oxide Dispersion Strengthened (ODS) Steel

Idaho National Laboratory - Materials and Fuels Complex (MFC)

Janelle Wharry

Purdue University

Synergistic ODS Nanocluster Irradiation Evolution and Radiation-Induced Segregation

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

Jian Wang

University of Nebraska-Lincoln

In-situ observation of microstructural stability under dual-beam irradiation in interface/microstructure-manipulated nickel alloys

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

Jose Arregui-Mena

Oak Ridge National Laboratory

Investigation of the irradiation induced porosity in concrete aggregates with x-ray computed tomography and helium pycnometry

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

Jung-Kun Lee

University of Pittsburgh

Investigation of Irradiation-assisted Stress Corrosion Cracking of Additively Manufactured Austenitic Stainless Steel

University of Michigan - Michigan Ion Beam Laboratory (MIBL)

Junhua Jiang

Idaho National Laboratory

Ion-Irradiation and Microstructural Change Studies of Glassy Carbon

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

Kelvin Xie

Texas A&M University

Determination of spatial and chemical relationship of hydrogen and helium in 316 SS PWR flux thimble tube at 76 dpa for extrapolation into beyond-40-year operation

Idaho National Laboratory - Materials and Fuels Complex (MFC)

Kieran Dolan

Massachusetts Institute of Technology

Impact of neutron damage and microstructure changes on hydrogen retention in nuclear graphite

Massachusetts Institute of Technology - Nuclear Reactor Laboratory

Li He

University of Wisconsin

Examining microstructural evolution of HT9 under neutron and ion irradiations from 370 °C to 570 °C

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

Ling Wang

University of Tennessee-Knoxville

Sink strength dependent coherency loss of precipitates during in-situ ion irradiation of fcc-structured model binary alloys

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

Maalavan Arivu

Missouri University of Science and Technology

Correlative Transmission Electron Microscopy and Atom Probe Tomography Study of Radiation Induced Segregation and Precipitation in Nanostructured SS304

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

Michael Reichenberger

Idaho National Laboratory

Irradiation of Nb-93 targets for ASTM International Inter-Laboratory Study of E1297, “Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium”.

Idaho National Laboratory - Materials and Fuels Complex (MFC)

Qing Su

University of Nebraska-Lincoln

Dual beam irradiation stability of amorphous silicon oxycarbide (SiOC)

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

Samuel A. Briggs

Oregon State University

Dose rate effects on irradiation-enhanced precipitation in FeCrAl alloys

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

Tyler Smith

University of Tennessee-Knoxville

The influence of second phase precipitates on hydride reorientation in spent nuclear fuel cladding

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

Xiang Liu

Idaho National Laboratory

Investigation of fission gas bubble distribution, phase transformations, and bubble growth kinetics in a FFTF-irradiated U-10Zr fuel

Idaho National Laboratory - Materials and Fuels Complex (MFC)

Yong Yang

University of Florida

Understand the Fission Products Behavior in UCO Fuel Kernels of safety tested AGR2 TRISO Fuel Particles by Using Titan Themis 200 with ChemiSTEM Capability

Idaho National Laboratory - Materials and Fuels Complex (MFC)

Yu Lu

University of Florida

Predict the mechanical behavior of irradiated cast stainless steels based on the microstructures and measured properties from nanoindentation

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

Zefeng Yu

University of Wisconsin

High resolution (S)TEM/EDS characterization of neutron irradiated commercial Zr-Nb alloys

Idaho National Laboratory - Materials and Fuels Complex (MFC)

Ramprashad Prabhakaran

 

Pacific Northwest National Laboratory

 

Mechanical characterization of neutron irradiated NF616 (T92) as a function of doses and temperatures

 

Idaho National Laboratory - Materials and Fuels Complex (MFC) and Pacific Northwest National Laboratory - Radiochemical Processing Laboratory

Eda Aydogan

 

Sabanci University

 

Effect of interstitial elements on the irradiation response of HT9 tempered ferritic/martensitic steels

 

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



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