Projects

NSUF 16-CINR-10393: Irradiation Testing of LWR Additively Manufactured Materials

The purpose of this proposed work is to perform full irradiation / PIE on...

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NSUF 16-CINR-10432: Fission Product Transport in TRISO

This program will measure diffusion coefficients of fission products (FP) for...

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NSUF 16-CINR-10468: Radial Heat Flux - Irradiation Synergism in SiC ATF Cladding

Synergism of neutron irradiation and high heat flux presents unique yet...

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NSUF 16-CINR-10480: Role of minor alloying elements on long range ordering in Ni-Cr alloys

High Cr, Ni-based alloys are an important class of structural materials due...

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NSUF 16-CINR-10537: Enhancing irradiation tolerance of steels via nanostructuring by innovative manufacturing techniques

Equal-channel angular pressing (ECAP) and high-pressure torsion (HPT) are two...

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NSUF 16-CINR-10584: Irradiation Performance Testing of Specimens Produced by Commercially Available Additive Manufacturing Techniques

The proposed project will collect first-ever irradiation performance data for...

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NSUF 16-CINR-10696: Understand the phase transformation of thermal aged and neutron irradiated duplex stainless steels used in LWRs

Complemented by the TEM/APT studies and ex-situ mechanical tests on duplex...

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NSUF 16-CINR-10764: Radiation-Enhanced Diffusion of Ag, Ag-Pd, Eu, and Sr in Neutron Irradiated PyC/SiC Diffusion Couples

The objective of the study is to investigate thermal diffusion and neutron...

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NSUF 16-CINR-10834: Effect of Gamma Irradiation on the Microstructure and Mechanical Properties of Nano-modified Concrete

Motivation. Extending the service life and performance of used nuclear fuel...

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NSUF 16-CINR-639: Beamline Examination of a Hf-Al Metal-Matrix Composite Material

This project proposes to conduct post-irradiation examination of HfAl3 Al...

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NSUF 17-1001: APT and TEM study of redistribution of alloying elements in ZrNb alloys following proton irradiation: effects on in-reactor corrosion kinetics.

We propose to study the effect of proton irradiation on Nb redistribution...

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NSUF 17-1014: Radiation-Hardening and Microstructural Stability of NF709 Austenitic Stainless Steel

Austenitic stainless steel NF709 has been down-selected for development as a...

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NSUF 17-1016: Site-specific Atom Probe Tomography Characterisation of Grain Boundaries in Archival Surveillance Steels From Advanced Test Reactor (ATR-2) Neutron Irradiation Experiment

This proposal focuses on the site-specific characterisation, via atom probe...

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NSUF 17-1023: Hardness profiling of ion irradiated 15-15Ti cladding steel using CSM nano-indentation

This work proposes CSM nano-indentation on self-ion irradiated 15-15Ti...

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NSUF 17-1025: 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

This proposal covers characterization of a set of advanced RPV alloys by atom...

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NSUF 17-1028: Microstructural Examination of Neutron Irradiated Al-HfAl3 Metal Matrix Composite Materials for Application to Neutron Spectrum Modification in Nuclear Reactors

Al-HfAl3 metal matrix composite (MMC) materials are under consideration for...

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NSUF 17-1029: Irradiation responses of ultrastrong nano precipitation martensite steel

The objective of this proposal is to study irradiation responses of a...

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NSUF 17-1032: Radiation Tolerance of Advanced Joining Techniques for Oxide Dispersion Strengthened Steels under Ion Irradiation

The objective of this work is to examine the effect of high damage levels of...

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NSUF 17-1033: Pore size distribution in U-Mo fuel irradiated to low burnup

Attaining fundamental understanding of fuel performance requires detailed...

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NSUF 17-1042: Microstructural characterization of 13% burn-up MOX fuel