U.S. DOE Nuclear Science User Facilities Awards 35 Rapid Turnaround Experiment Research Proposals

U.S. Department of Energy Nuclear Science User Facilities Awards 35 Rapid Turnaround Experiment Research Proposals

 

IDAHO FALLS -- The U.S. Department of Energy (DOE) Nuclear Science User Facilities (NSUF) has selected 35 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 35 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 industry, eleven universities, and four national laboratories who will work with the NSUF on their proposed experiments. The newly awarded RTE projects are:

PI Name

Institution

Title

Facility

Adrien Couet

University of Wisconsin

Characterization of Oxide Layer on the Surface of High Temperature Water Corroded Zircaloy-4 In the Presence of Neutron+Gamma and Gamma Only

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

Adrien Couet

University of Wisconsin

APT and TEM study of redistribution of alloying elements in ZrNb alloys following proton irradiation: effects on in-reactor corrosion kinetics.

Center for Advanced Energy Studies Microscopy and Characterization Suite

Bei Ye

Argonne National Laboratory

Investigation of irradiation-induced recrystallization in U-Mo fuel

Center for Advanced Energy Studies Microscopy and Characterization Suite

Ben Maier

University of Wisconsin

Atomic Probe Tomography Studies of Irradiated Cold Spray Coatings for Accident Tolerant Cladding

Center for Advanced Energy Studies Microscopy and Characterization Suite

Benjamin Jenkins

University of Oxford

Site-specific Atom Probe Tomography Characterisation of Grain Boundaries in Archival Surveillance Steels From Advanced Test Reactor (ATR-2) Neutron Irradiation Experiment

Center for Advanced Energy Studies Microscopy and Characterization Suite

Cem Topbasi

Electric Power Research Institute

In Situ Transmission Electron Microscopy Study of Radiation Damage Effects on the d-Hydride Microstructure in Irradiated Zircaloy-4

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

Chi Xu

University of Florida

An in-situ TEM characterization of tensile testing of ion irradiated HT-UPS steel at RT and 400°C

Argonne National Laboratory – Intermediate Voltage Electron Microscope Tandem Facility

PI Name

Institution

Title

Facility

David Carpenter

Massachusetts Institute of Technology

Post-irradiation analysis of hybrid metallic coatings on SiC after neutron irradiation 290-330°C

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

Djamel Kaoumi

North Carolina State University

Ion irradiation response of nanostructured alloys: In-situ TEM observations vs. ex-situ characterization

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 1.94 MGy with respect to non-irradiated samples

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

Erik Mader

Electric Power Research Institute

AsTeROID (follow-on AsTeR (Advanced Test Reactor) project to Optimize hydrogen-assisted Irradiation growth and Dimensional stability)

Idaho National Laboratory Materials and Fuels Complex

Gabriel Meric de Bellefon

University of Wisconsin

The effectiveness of coherent and incoherent twin boundaries in alleviating radiation damage in heavy-ion-irradiated 316L austenitic stainless steels

Argonne National Laboratory – Intermediate Voltage Electron Microscope Tandem Facility

Elizabeth Getto

United States Naval Academy

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

University of Michigan - Michigan Ion Beam Laboratory

Haiming Wen

Idaho State University

Enhanced irradiation tolerance of high-entropy alloys

University of Wisconsin Tandem Accelerator Ion Beam/ Characterization Laboratory

Konstantina Lambrinou

SCK•CEN

Study of the factors affecting the radiation tolerance of MAX phases for innovative fuel cladding concepts

University of Michigan - Michigan Ion Beam Laboratory

Kumar Sridharan

University of Wisconsin

Heavy ion irradiation and ex situ transmission electron microscopy study of the effectiveness of twin boundaries in alleviating radiation damage in 316 austenitic stainless steels

University of Wisconsin Tandem Accelerator Ion Beam/ Characterization Laboratory

Lin Shao

Texas A&M University

Post-irradiation observation following high-rate self-ion irradiation of previously neutron-irradiated 304 stainless steel

Center for Advanced Energy Studies Microscopy and Characterization Suite

Mukesh Bachhav

Idaho National Laboratory

Microstructure and microchemical characterization of neutron and proton irradiated Alloy D9 using APT and TEM

Center for Advanced Energy Studies Microscopy and Characterization Suite

Mukesh Bachhav

Idaho National Laboratory

Effect of Phosphorous (P) on precipitation and segregation behavior in neutron irradiated Reactor Pressure Vessel steels in the Advanced Test Reactor (ATR-2): An Atom Probe study.

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 Advanced Reactor Pressure Vessel Super Clean Steels in the UCSB Advanced Test Reactor (ATR-2) Neutron Irradiation Experiment

Center for Advanced Energy Studies Microscopy and Characterization Suite

Niels Cautaerts

SCK•CEN

Hardness profiling of ion irradiated 15-15Ti cladding steel using CSM nano-indentation

University of California–Berkeley

 

 

 

PI Name

Institution

Title

Facility

Philip Edmondson

Oak Ridge National Laboratory

In situ amorphization studies of forsterite, diopside and quartz under ion irradiation

Argonne National Laboratory – Intermediate Voltage Electron Microscope Tandem Facility

Riley Parrish

University of Florida

Microstructural characterization of 13% burn-up MOX fuel

Idaho National Laboratory Materials and Fuels Complex

Riley Parrish

University of Florida

Microstructural characterization of 21% burn-up MOX fuel

Idaho National Laboratory Materials and Fuels Complex

 

Rodney Ewing

Stanford University

Radiation tolerance of Mn+1AXn phase nuclear fuel cladding materials

Argonne National Laboratory – Intermediate Voltage Electron Microscope Tandem Facility

Sebastien Teysseyre

Idaho National Laboratory

Characterization of Grain Boundary Damage in Highly Irradiated Specimens Exposed to Irradiation Assisted Stress Corrosion Cracking.

University of California–Berkeley

Sebastien Teysseyre

Idaho National Laboratory

Characterization of the Stability of the Microstructure of Novel ODS Alloys

Center for Advanced Energy Studies Microscopy and Characterization Suite

Steven Zinkle

University of Tennessee

Irradiation responses of ultrastrong nano precipitation martensite steel

Center for Advanced Energy Studies Microscopy and Characterization Suite

Tianyi Chen

Oak Ridge National Laboratory

Radiation-Hardening and Microstructural Stability of NF709 Austenitic Stainless Steel

Center for Advanced Energy Studies Microscopy and Characterization Suite

Todd Allen

University of Wisconsin

Examining microstructural differences in irradiated HT9, correlated with differences in processing prior to irradiation

Idaho National Laboratory Materials and Fuels Complex

Todd Allen

University of Wisconsin

IVEM investigation of defect evolution in FCC and BCC HEAs during heavy ion irradiation

Argonne National Laboratory – Intermediate Voltage Electron Microscope Tandem Facility

Weiying Chen

Argonne National Laboratory

Fundamental Study of Alloying Complexity Effects on the Irradiation Process in High Entropy Alloys

Argonne National Laboratory – Intermediate Voltage Electron Microscope Tandem Facility

Yong Yang

University of Florida

Characterize the Irradiated Microstructure and Understand the Fission Product Behavior in an Irradiated and Safety Tested AGR-1 TRISO Fuel Particle New Proposal

Idaho National Laboratory & Center for Advanced Energy Studies

Yuanyuan Zhu

Pacific Northwest National Laboratory

Microstructural Examination of Neutron Irradiated Al-HfAl3 Metal Matrix Composite Materials for Application to Neutron Spectrum Modification in Nuclear Reactors

Pacific Northwest National Laboratory

Zheng Zhang

University of Florida

Pore size distribution in U-Mo fuel irradiated to low 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 October 12, 2017.

 

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

 

INL is a DOE multi-program 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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