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, 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 Sevart, 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 Sevart, 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 Sevart, Daniele Salvato, Tiankai Yao, Cynthia Adkins, Luca Capriotti, Assel Aitkaliyeva, NSUF Annual Program Review April 15-17, (2025)

Additional Publications:

	"Microstructurally validated stable and predictable swelling in low-enriched uranium monolithic U-10Mo fuel mini-plates" Daniele Salvato, Adam B. Robinson, Nancy J. Lybeck, Jan-Fong Jue, Tammy L. Trowbridge, Jatuporn Burns, Fidelma G. Di Lemma, Charlyne A. Smith, Margaret A. Marshall, Dennis D. Keiser Jr., Jeffrey J. Giglio, James I. Cole, William A. Hanson, [2025] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2025.155746
	"Microstructural and micromechanical characterization of Cr diffusion barrier in ATR irradiated U-10Zr metallic fuel" Cameron B. Howard, Fei Xu, Daniele Salvato, Kaustubh K. Bawane, Daniel J. Murray, David M. Frazer, Scott T. Anderson, Tiankai Yao, Sunghwan Yeo, June-Hyung Kim, Byoung-Oon Lee, Jun Hwan Kim, Randall S. Fielding, Luca Capriotti, Yachun Wang, [2024] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2024.155231
	"Analysis of radially resolved thermal conductivity in high burnup mixed oxide fuel and comparison to thermal conductivity correlations implemented in fuel performance codes" Tsvetoslav Pavlov, Narayan Poudel, Daniele Salvato, Chuting Tsai, Brian Merritt, Alex Hansen, Troy Munro, Fabiola Cappia, Marat Khafizov, Joshua Ferrigno, [2024] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2024.155090
	"Effect of heat treatment on the microstructure of medium burn-up U-Mo monolithic fuel foils" T.L. Trowbridge, J.F. Jue, D. Salvato, S. Anderson, C.A. Smith, B.D. Miller, D.D. Keiser, J.J. Giglio, J.I. Cole, F.G. Di Lemma, [2024] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2024.155002
	"The effect of temperature and burnup on U-10Zr metallic fuel chemical interaction with HT-9: A SEM-EDS study" Kyle M. Paaren, Jacob A. Hirschhorn, Larry K. Aagesen, Fei Xu, Fidelma Giulia Di Lemma, Luca Capriotti, Tiankai Yao, Daniele Salvato, [2024] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2024.154928
	"Contributions to the mechanistic understanding of the microstructural evolution in irradiated U-Mo dispersion fuel" Charlyne A. Smith, Tsvetoslav R. Pavlov, William A. Hanson, Kaustubh K. Bawane, Mukesh N. Bachhav, Brandon D. Miller, Tammy L. Trowbridge, Jian Gan, Jeffrey J. Giglio, Alexander J. Winston, Jody L. Henley, Adam B. Robinson, Dennis D. Keiser, Irina Y. Glagolenko, B. Ye, Z.-G. Mei, Laura M. Jamison, Gerard L. Hofman, Abdellatif M. Yacout, Sven Van den Berghe, Ann Leenaers, Daniele Salvato, [2024] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2023.154789
	"Impact of SEM acquisition parameters on the porosity analysis of irradiated U-Mo fuel" C.A. Smith, B. Ye, Z.-G. Mei, A.M. Yacout, J. Van Eyken, B.D. Miller, D.D. Keiser, I.Y. Glagolenko, J.J. Giglio, A.B. Robinson, A. Leenaers, J. Wight, J.L. Henley, D. Salvato, [2023] Nuclear Materials and Energy · DOI: 10.1016/j.nme.2023.101469
	"The role of UC inclusions in the development of fission gas bubble superlattice neutron-irradiated monolithic U-10Mo fuels" Kaustubh Bawane, Jian Gan, Dennis Keiser, Daniele Salvato, Mukesh Bachhav, Jan-Fong Jue, Charlyne Smith, [2023] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2023.154474
	"Early self-organization of fission gas bubble superlattice formation in neutron-irradiated monolithic U-10Mo fuels" Kaustubh Bawane, Daniele Salvato, Mukesh Bachhav, Dennis Keiser, Brandon Miller, Jian Gan, Jan-Fong Jue, Dong Choe, Paul Gilbreath, William Hanson, Charlyne Smith, [2023] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2023.154358
	"Transmission electron microscopy characterization of the fuel-cladding chemical interactions in HT9 cladded U-10Zr fuel" Brandon D. Miller, Jason M. Harp, Daniele Salvato, Luca Capriotti, Tiankai Yao, Yachun Wang, [2022] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2022.153990
	"Transmission electron microscopy study of a high burnup U-10Zr metallic fuel" Xiang Liu, Daniel J. Murray, Kyle M. Paaren, Fei Xu, Tsvetoslav Pavlov, Michael T. Benson, Luca Capriotti, Tiankai Yao, Daniele Salvato, [2022] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2022.153963
	"Temperature Effects on Interdiffusion of Al and U-Mo under Irradiation" Y. Miao, J. Shi, D. Salvato, K. Mo, L. Jamison, A. Bergeron, G.L. Hofman, A. Leenaers, A. Oaks, A.M. Yacout, S. Van den Berghe, W. Petry, Y.S. Kim, B. Ye, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2020.152684 · EID: 2-s2.0-85096852627 · ISSN: 0022-3115
	"U(Mo) grain refinement induced by irradiation with high energy iodine" J. Shi, H. Breitkreutz, W. Van Renterghem, B. Baumeister, C. Schwarz, A. Leenaers, S. Van den Berghe, C. Detavernier, W. Petry, D. Salvato, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2021.152850 · EID: 2-s2.0-85100666749 · ISSN: 0022-3115
	"Corrigendum to “Pore pressure estimation in irradiated UMo” [J. Nucl. Mater. 510 (2018) 472–483] (Journal of Nuclear Materials (2018) 510 (472–483), (S0022311518305749), (10.1016/j.jnucmat.2018.08.039))" A. Leenaers, S. Van den Berghe, C. Detavernier, D. Salvato, [2020] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2020.152393 · EID: 2-s2.0-85088787520 · ISSN: 0022-3115
	"The initial formation stages of a nanobubble lattice in neutron irradiated U(Mo)" [2020] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2019.151947 · EID: 2-s2.0-85076559400 · ISSN: 0022-3115
	"Pore pressure estimation in irradiated UMo" A. Leenaers, S. Van den Berghe, C. Detavernier, D. Salvato, [2018] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2018.08.039 · EID: 2-s2.0-85052299438 · ISSN: 0022-3115
	"Spark plasma sintering of fine uranium carbide powder" J.-F. Vigier, M. Cologna, L. Luzzi, J. Somers, V. Tyrpekl, D. Salvato, [2017] Ceramics International · DOI: 10.1016/j.ceramint.2016.09.136 · EID: 2-s2.0-84996564385 · ISSN: 0272-8842
	"Innovative preparation route for uranium carbide using citric acid as a carbon source" J.-F. Vigier, O. Dieste Blanco, L. Martel, L. Luzzi, J. Somers, V. Tyrpekl, D. Salvato, [2016] Ceramics International · DOI: 10.1016/j.ceramint.2016.07.138 · EID: 2-s2.0-84994234421 · ISSN: 0272-8842
Source: ORCID/CrossRef using DOI

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