U.S. DOE Nuclear Science User Facilities Awards 30 Rapid Turnaround Experiment Research Proposals

U.S. Department of Energy's Nuclear Science User Facilities Awards 30 Rapid Turnaround Experiment Research Proposals


IDAHO FALLS -- The U.S. Department of Energy (DOE) Nuclear Science User Facilities (NSUF) has selected 30 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 30 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 individuals from two nuclear energy industries, 14 universities, and 6 national laboratories who will work with the NSUF on their proposed experiments. The newly awarded RTE projects are:

 

PI Name

Institution

Title

Facility

Aida Amroussia

Michigan State University

Post-irradiation characterization of ion irradiation damage in Ti-6Al-4V and CP-Ti : Influence of the microstructure and temperature

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

Alicia Raftery

Purdue University

Pre-characterization of DISECT UMo fuel samples

Idaho National Laboratory & Center for Advanced Energy Studies

Caleb Massey

University of Tennessee Knoxville

Nano-precipitate Response to Neutron Irradiation in Model ODS FeCrAl Alloy 125YF

Center for Advanced Energy Studies Microscopy and Characterization Suite

Cheng Sun

Idaho National Laboratory

Nanoindentation testing of neutron irradiated 304 stainless steels hex-blocks

Center for Advanced Energy Studies Microscopy and Characterization Suite

Chris Grovenor

Oxford University

In situ ion irradiation of second phase particles in zirconium fuel cladding

Argonne National Laboratory – Intermediate Voltage Electron Microscope Tandem Facility

Elena Tajuelo Rodriguez

Oak Ridge National Laboratory

Changes on viscoelastic behavior, morphology and chemical structure of gamma irradiated calcium silicate hydrates to 0.96MGy with respect to non-irradiated samples

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

Elizabeth Getto

United States Naval Academy

Radiation Tolerance of Friction Stir Welded Ferritic Oxide Dispersed Steel under Ion Irradiation

Center for Advanced Energy Studies Microscopy and Characterization Suite

Emmanuelle Marquis

University of Michigan

a' precipitation in neutron-irradiated Fe-9/12Cr alloys

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

Gabriel Meric de Bellefon

University of Wisconsin - Madison

Sample Preparation for Ex-situ Transmission Electron Microscopy Study of Deformation-induced Twinning and Martensite in Two 316L Austenitic Stainless Steels: Role of Stacking Fault Energy and Grain Orientation

Center for Advanced Energy Studies Microscopy and Characterization Suite

Haiming Wen

Idaho State University

Atom Probe Tomography Study of Neutron Irradiated U-Mo Fuel

Idaho National Laboratory & Center for Advanced Energy Studies

Ian Robertson

University of Wisconsin-Madison

Enhancing radiation tolerance through increasing alloy complexity

Argonne National Laboratory – Intermediate Voltage Electron Microscope Tandem Facility

Jacqueline Stevens

AREVA NP Inc.

Hydrogen Analysis and Oxide Characterization of Reactor Irradiated Zr-Nb Alloy

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

Janelle Wharry

Purdue University

Radiation induced segregation and phase separation in neutron irradiated FeCrAl alloys

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

Jie Lian

Rensselaer Polytechnic Institute

Fission Gas Behavior and Fuel Swelling of Accident Tolerant U3Si2 Fuels by Ion Beam Irradiation

Argonne National Laboratory – Intermediate Voltage Electron Microscope Tandem Facility

Jiming Bao

University of Houston

Post Irradiation Examination of Fiber Optic Temperature Sensors for In-Pile Temperature Monitor and Control for Advanced Test Reactor

Idaho National Laboratory Materials and Fuels Complex

Jonathan Tatman

Electric Power Research Institute

SEM, EBSD, and TEM Investigation of Irradiated Austenitic Stainless Steel Weldment

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

Ju Li

Massachusetts Institute of Technology

The in-situ observation of radiation resistance mechanism in metal-1D/2D nanocomposites for structural material and fuel cladding of next generation reactors 

Argonne National Laboratory – Intermediate Voltage Electron Microscope Tandem Facility

Lingfeng He

Idaho National Laboratory

Investigation of gas bubble behavior under ion irradiation

Argonne National Laboratory – Intermediate Voltage Electron Microscope Tandem Facility

Mahmut Cinbiz

Oak Ridge National Laboratory

In situ TEM Study of the Ion Irradiation Damage on Hydrides in a Zirconium Alloy for Nuclear Fuel Cladding

Argonne National Laboratory – Intermediate Voltage Electron Microscope Tandem Facility

Ming Tang

Los Alamos National Laboratory

Radiation Stability Study on Nuclear Waste/Spent Fuel Materials

Argonne National Laboratory – Intermediate Voltage Electron Microscope Tandem Facility

Mitra Taheri

Drexel University

Quantitative assessment of the role of interfaces and grain boundaries in the development of radiation tolerant nuclear materials

Argonne National Laboratory – Intermediate Voltage Electron Microscope Tandem Facility

Niels Cautaerts

SCK-CEN

Characterization of ion irradiated 15-15Ti steel by APT

Center for Advanced Energy Studies Microscopy and Characterization Suite

Osman El Atwani

Los Alamos National Laboratory

Performance of  Nanocrystalline and Ultrafine Tungsten Under Irradiation and Mechanical Extremes

Argonne National Laboratory – Intermediate Voltage Electron Microscope Tandem Facility

Ramprashad Prabhakaran

Pacific Northwest National Laboratory

Mechanical characterization of neutron irradiated FSW ODS alloys

Pacific Northwest National Laboratory

Riley Parrish

University of Florida

Microstructural characterization of 3% burn-up MOX fuel

Idaho National Laboratory Materials and Fuels Complex

Samuel A. Briggs

Sandia National Laboratories

Study of nanocluster stability in neutron- and ion-irradiated ODS FeCrAl alloys

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

Vijay Vasudevan

University of Cincinnati

Effect of grain boundary character and surface treatment on irradiation tolerance of nuclear alloys

Center for Advanced Energy Studies Microscopy and Characterization Suite

Yutai Katoh

Oak Ridge National Laboratory

Micromechanical properties of interfacial elements in advanced SiC composite and its environmentally protective coatings

University of California–Berkeley

Zhangbo Li

University of Florida

TEM investigation of radiation damage of ferrite in CF-3

Center for Advanced Energy Studies Microscopy and Characterization Suite

Zheng Zhang

University of Florida

Pore size distribution in U-Mo fuel irradiated to high burnup

Idaho National Laboratory Materials and Fuels Complex

 

NSUF holds RTEs 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 May 31, 2017.

 

For user guides and more information about submitting proposals, visit the NSUF website, https://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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