Daniele Salvato

Profile Information

Name

dr Daniele Salvato

Institution

Idaho National Laboratory

Position

PostDoc

h-Index

ORCID

0000-0002-1866-6500

Biography

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).

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.

Expertise

EBSD, EDS, FIB, Ion Irradiation, Microstructure, Neutron Irradiation, PIE, SEM, TEM

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 Tan, Troy Munro, Fabiola Cappia, Journal of Nuclear Materials Vol. 596 2024 Link

Accomplishments

NSUF Profile

This NSUF Profile is 95% Complete

NSUF Author

Authored 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

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

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, #5000

NSUF Research Collaborations

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

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

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

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

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, #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, #4769

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