Daniele Salvato

Profile Information
Name
dr Daniele Salvato
Institution
Idaho National Laboratory
Position
PostDoc
h-Index
ORCID
0000-0002-1866-6500
Biography
<p>I got a Bachelor in Energy Engineering and a Master in Nuclear Engineering from Politecnico di MIlano (Italy). In 2020, I obtained a PhD at the Belgian Nuclear Research Centre (SCK CEN), in collaboration with the University of Gent (Belgium). I am currently working as a postdoc in the post irradiation examination group of the Idaho National Laboratory (USA).&nbsp;</p><p>My interests and job functions relates to the post irradiation characterization of nuclear fuel, focusing on how fuel microstructure and thermal-mechanical properties are affected by neutron (and ion) irradiation. During my studies and my time at the Idaho National Laboratory, I have been using various electron microscopy techniques to examine neutron or ion irradiated fuels, such as SEM, TEM, EBSD, EPMA.</p>
Expertise
EBSD, EDS, Ion Irradiation, Microstructure, Neutron Irradiation, SEM
Publications:
"Analysis of radially resolved thermal conductivity in high burnup mixed oxide fuel and comparison to thermal conductivity correlations implemented in fuel performance codes" Marat Khafizov, Joshua Ferrigno, Tsvetoslav Pavlov, Narayan Poudel, Daniele Salvato, Chuting Tsai, Troy Munro, Fabiola Cappia, Journal of Nuclear Materials Vol. 596 2024 Link
Presentations:
"Investigating Microstructural and Local Thermal Conductivity Changes in Irradiated U-Zr Annular Fuel" Mary Meyer, Daniele Salvato, Mitchell Mika, Fei Xu, Tiankai Yao, Luca Capriotti, Assel Aitkaliyeva, TMS 2025 March 23-27, (2025)
"Investigation of Constituent Redistribution in a 12 at.% Burn-up Annular U-10Zr Fuel Using EPMA and TEM" Mary Meyer, Karen Wright, Daniele Salvato, Fei Xu, Tiankai Yao, Assel Aitkaliyeva, ANS Annual Meeting June 15-18, (2025)
"Thermal Conductivity Measurements of Irradiated Annular Low Burn-up U-10Zr Fuel" Mary Meyer, Daniele Salvato, Tiankai Yao, Cynthia Adkins, Luca Capriotti, Assel Aitkaliyeva, NSUF Annual Program Review April 15-17, (2025)
Accomplishments

NSUF Profile

This NSUF Profile is 95% Complete

NSUF Author

Authored an NSUF-supported publication

NSUF Presenter

Presented an NSUF-supported publication

Accomplished Submitter

Submitted 3+ RTE Proposals to NSUF

NSUF Researcher

Awarded an RTE Proposal

Accomplished Collaborator

Collaborated on 3+ RTE Proposals

NSUF Supported Research

Stability limits of the gas bubble superlattice in neutron irradiated U-Mo fuel: A 3D multi-modal and multi-scale study - FY 2024 RTE 2nd Call, #24-5000

Quantification of local burnup in irradiated U-10Zr metallic fuel using Atom Probe Tomography - FY 2023 RTE 3rd Call, #23-4774
NSUF Research Collaborations

Thermal Conductivity Measurements of Irradiated Annular Low Burn-Up U-10Zr Fuel - FY 2024 RTE 2nd Call, #24-4956

Advanced characterization of irradiated FAST aLEU U-Mo rodlets using Transmission Electron Microscopy and Atom Probe Tomography - FY 2024 RTE 2nd Call, #24-4952

Porosity Evolution in High Burnup and Low Irradiation Temperature U-10wt.%Zr Fuel Subregions - FY 2024 RTE 2nd Call, #24-4939

Fuel – Cladding Chemical Interaction of U10Zr Fuel and HT-9 Cladding Using in situ Heated TEM - FY 2024 RTE 1st Call, #24-4855

Post-Irradiation Analysis of U-Pu-Zr Fuel Incorporating Am and Np Actinides: Fuel-Cladding Interactions in EBR-II and Advanced Microscopic Examination - FY 2024 RTE 1st Call, #24-4847

Probing the Chemical composition and Charge Status of Secondary Phases and Precipitates in High Burnup Metallic Fuel using Nano-SIMS and TEM-EELS - FY 2023 RTE 3rd Call, #23-4769

Serial Sectioning to Quantify Fission Induced Microstructural Evolution in U-Zr Alloys - FY 2023 RTE 1st Call, #23-4593

Fission product partitioning behavior in irradiated monolithic U-Mo fuels - FY 2022 RTE 1st Call, #22-4412