Department of Energy Nuclear Science User Facilities Awards 39 Rapid Turnaround Experiment Research Projects

IDAHO FALLS -- The U.S. Department of Energy (DOE) Nuclear Science User Facilities (NSUF) has selected 39 new Rapid Turnaround Experiment (RTE) projects, totaling up to approximately $1.3 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 39 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 26 principal investigators from universities, 10 from national laboratories, two from foreign institutions, 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

Charlyne Smith

University of Florida

Atom probe tomography of fission gas bubble superlattice in U-Mo fuel

Center for Advanced Energy Studies - Microscopy and Characterization Suite

David Estrada

Boise State University

Ion irradiation of Aerosol Jet Printed Cu, Ag, and Ni Structures

University of Michigan Michigan Ion Beam Laboratory

David Frazer

University of California Berkeley

Elevated Temperature In-situ SEM micro compression of UO2

University of California Berkeley

Edward Lahoda

Westinghouse

Evaluation of Irradiated Cr Coatings on Zirconium Alloys

Westinghouse Materials Center for Excellence

Isabella Van Rooyen

Idaho National Laboratory

In-situ High Temperature Ion Irradiation Transmission Electron Microscopy to Understand Fission Product Transport in Silicon Carbide of TRISO Fuel

Sandia National Laboratory I3TEM Facility

James Edgar

Kansas State University

Transmutation doping of hexagonal boron nitride

The Ohio State University

James Spicer

Johns Hopkins University

 Understanding the mechanism for mesopore development in irradiated graphite by high resolution gas adsorption measurements (N2 and Kr at 77 K)

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

James Stubbins

University of Illinois

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

Idaho National Laboratory Materials and Fuels Complex

Janelle Wharry

Purdue University

Extension and Validation of Rate Theory Model of Nanocluster Irradiation Evolution: An Atom Probe Tomography Study

Center for Advanced Energy Studies - Microscopy and Characterization Suite

Jean Claude van Duysen

University of Tennessee

In Situ Straining of 10-dpa Neutron Irradiated Austenitic Stainless Steels using Scanning Electron Microscope Electron Backscatter Diffraction

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

Jian Gan

Idaho National Laboratory

Investigation of gas bubble behavior in metals using in-situ Ne, Ar and Kr ion irradiation

Argonne National Laboratory  Intermediate Voltage Electron Microscopy Tandem Facility

Jonova Thomas

Purdue University

Microstructural Phase Characterization of Irradiated and Control U-10Zr Fuels

Idaho National Laboratory Materials and Fuels Complex

Ju Li

Massachusetts Institute of Technology

Quantification of porosity evolution in ion irradiated metal-1D/2D nanocomposites and gas-embrittled steels via Positron Annihilation Spectroscopy

North Carolina State University

Julie Tucker

Oregon State University

Micro-mechanical characterization of long range order in Ni-Cr alloys and their response to radiation damage

University of California Berkeley

Karl Whittle

University of Liverpool

Interfacial Effects, Damage and Recovery in Binary Carbides

Argonne National Laboratory Intermediate Voltage Electron Microscopy Tandem Facility

Kathy Lu

Virginia Tech

In situ TEM observation of microstructural evolution of silicon carbide (SiC)-nanostructured ferritic alloy (NFA) composite under high temperature ion irradiation

Argonne National Laboratory  Intermediate Voltage Electron Microscopy Tandem Facility

Kayla Yano

Purdue University

TEM in situ 4-point bend fracture testing of irradiated ODS alloys

Center for Advanced Energy Studies - Microscopy and Characterization Suite

Kevin Tolman

Idaho National Laboratory

Towards characterizing the microstructural evolution in nuclear fuel via neutron diffraction

Massachusetts Institute of Technology

Koroush Shirvan

Massachusetts Institute of Technology

Understanding the Mechanism of Thermal-Hydraulic Enhancement On Gamma Irradiated Nuclear Materials Interfaces

Sandia National Laboratory

Gamma Irradiation Facility

Lingfeng He

Idaho National Laboratory

Characterization of grain boundaries of Alloy X-750 irradiated in EBR-II

Idaho National Laboratory Materials and Fuels Complex

Maria A Auger

University of Oxford

Post-irradiation analysis at the nanoscale of 14YWT after high dose (16.6 dpa) neutron irradiation at 386C and 412C

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

Maria Okuniewski

Purdue University

Synchrotron X-ray Characterization of the Microstructural Evolution of U Alloys Irradiated to Low Fluences

Brookhaven National Laboratory

Matthew Cook

University of Florida

Fission Product Distribution Comparison in Irradiated and Safety Tested AGR-1 and AGR-2 TRISO Fuel Particles

University of Florida

Matthew Swenson

University of Idaho

Irradiation-induced solute clustering behavior in ferritic/martensitic alloy T91

Center for Advanced Energy Studies - Microscopy and Characterization Suite

Michael Short

Massachusetts Institute of Technology

Investigation of radiation-generated phases in FeCrSi alloys for multimetallic layered composite (MMLC) for LWR fuel cladding

Center for Advanced Energy Studies - Microscopy and Characterization Suite

Mukesh Bachhav

Idaho National Laboratory

Understanding the role of grain boundary character in segregation behavior of solute elements in neutron irradiated 304 SS using Atom Probe Tomography.

Center for Advanced Energy Studies - Microscopy and Characterization Suite

Nathan Almirall

University of California Santa Barbara

Atom Probe Tomography Investigations of nm-Scale Precipitates in Reactor Pressure Vessel Steels in the UCSB Advanced Test Reactor (ATR-2) Neutron Irradiation Experiment

Center for Advanced Energy Studies - Microscopy and Characterization Suite

Nicholas Brown

Penn State University

Kinetics of irradiation defect annealing and thermal conductivity recovery in silicon carbide at high temperature

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

Ramprashad Prabhakaran

Pacific Northwest National Laboratory

Mechanical characterization of three heats (ORNL, LANL and EBR II) of HT-9 after side-by-side neutron irradiation at LWR and fast reactor relevant temperatures

Pacific Northwest National Laboratory

Riley Parrish

University of Florida

Microstructural characterization of ~7% burn-up MOX fuel

Idaho National Laboratory Materials and Fuels Complex

Rodney Ewing

Stanford University

In situ study of “rim effect” microstructure modification of nuclear fuels (resubmitted)

Argonne National Laboratory  Intermediate Voltage Electron Microscopy Tandem Facility

Steven Zinkle

University of Tennessee

Irradiation-induced precipitation/segregation in dual-phase Al0.3CoCrFeNi alloy

Center for Advanced Energy Studies - Microscopy and Characterization Suite

Subhashish Meher

Idaho National Laboratory

Electron Tomography for Three-Dimensional Characterization of Intragranular Fission Product Transport in Neutron-Irradiated Silicon Carbide in TRISO Fuel

Idaho National Laboratory Materials and Fuels Complex

Takaaki Koyanagi

Oak Ridge National Laboratory

Pair distribution function analysis on recovery of irradiation induced defects in SiC

Brookhaven National Laboratory

Tom Zega

University of Arizona

In situ Ion Irradiation of a SiC composite using a MEMS-based Heating Holder

Argonne National Laboratory Intermediate Voltage Electron Microscopy Tandem Facility

Xinghang Zhang

Purdue University

Radiation response of nanostructured steels with various types of defect sinks

Argonne National Laboratory  Intermediate Voltage Electron Microscopy Tandem Facility

Yinbin Miao

Argonne National Laboratory

In Situ TEM Investigation on Fission Gas Behavior in U-10Zr

Argonne National Laboratory  Intermediate Voltage Electron Microscopy Tandem Facility

Yong Yang

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 Using Titan Themis 200 with ChemiSTEM Capability

Idaho National Laboratory Materials and Fuels Complex

Yutai Katoh

Oak Ridge National Laboratory

Microstructural examination of in-situ tensile creep SiC specimen irradiated in the Halden reactor

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


NSUF holds RTE calls three times per year. The call offers any interested researcher from a university, national laboratory, or industry the opportunity to perform a limited scope of examinations at one facility. The next call for solicitations is scheduled to close February 28, 2018.

For user guides and more information about submitting proposals, visit the NSUF website, http://nsuf.inl.gov.

INL is a DOE multiprogram national laboratory, and performs work in each of DOE's strategic goal areas: energy, national security, science and environment. INL is the nation's leading center for nuclear energy research and development. Day-to-day management and operation of the laboratory is the responsibility of Battelle Energy Alliance.

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