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Dr. Arturo Bevilacqua

Ph.D. in Nuclear Engineering, Nuclear Engineer

 
 
 

Co-Founder, CEO

Dr. Arturo Bevilacqua, born in 1958 in Buenos Aires, Argentina, pursued his Nuclear Engineering degree at the Balseiro Institute in 1985, obtaining his Ph.D. in Nuclear Engineering in 1992. His extensive career includes research roles at the National Atomic Energy Commission of Argentina (CNEA) in San Carlos de Bariloche, Argentina, and the Institute for Transuranium Elements in Karlsruhe, Germany. 

 

From 2005 to 2010, he led the Nuclear Fuel Materials Development Division at INVAP S.E. and later joined the International Atomic Energy Agency (IAEA) in Vienna as a Spent Fuel Management Specialist until 2016. From 2019 to 2021, he was appointed Manager of the Radioactive Waste Management National Program of Argentina. 

 

Arturo has been a pivotal figure at CNEA in various capacities ever since. Throughout his career, he also taught nuclear materials and fuels at the Balseiro Institute, an Argentine academic institution that belongs to the National University of Cuyo and to the National Atomic Energy Commission. 

 

Bevilacqua's research predominantly surrounds nuclear fuel materials, spent fuel, and radioactive waste management. His significant contributions include a patented manufacturing method of a nuclear fuel rod for water-cooled power reactors, which uses uranium nitride as nuclear fuel material sheathed in silicon carbide, with a solid connection between the two provided by an interface material, silicon nitride or zirconium nitride, which converts the nuclear fuel rod into a monolithic element. 

 

Currently, he focuses on research into tailor-made fly ash-based inorganic polymer concrete as a green and sustainable alternative to ordinary Portland cement concrete as well as experimental research, development and innovation (RDI) of a green and sustainable Thermochemical Oxidation (TCO) chemistry process to produce single and mixed nanooxides for, among others, the energy (nuclear fuel materials and active materials for battery cathodes), healthcare (contrast materials), cosmetics (UV light filters), construction (green concrete), and petrochemical (catalysts) sectors. 

 

Furthermore, Arturo is deeply engaged in modeling and simulation work using the modules POLARIS, TRITON, ORIGEN-ARP, ORIGAMI and MAVRIC of the SCALE software suite for RDI of nuclear fuel materials for small modular reactors and large light and heavy water power reactors, production and shielding of radioisotopes for medical applications, and source term - mass, activity and decay power as well as alpha, beta, gamma and neutron spectra - and shielding calculations of spent nuclear fuel and radioactive waste. 


Arturo Bevilacqua serves as Senior International Expert, Consultant and Lecturer of the IAEA and for the period 2023-2028 he is appointed as the Associate Research Scientist of the IAEA Coordinated Research Project T13021 “Challenges and opportunities related to burnup and source terms of spent fuel from water-cooled SMRs”.

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"Sustainable nuclear power is vital for meeting Net-Zero Emissions Commitments within the framework of the United Nations Climate Action"

Selected Publications

 

SCALE Users' Group Workshop

A. Bevilacqua. Heterogeneous and Homogeneous NuFuel-HTP2 Fuel Assembly for NuScale. Technical Session - Best SCALE Model Contest. 2025 SCALE Users' Group Workshop. Presented Virtually from Oak Ridge National Laboratory (ORNL). June 2025.

IAEA Interregional Workshop 

A.M. Bevilacqua, A. Fernandez Zuvich. Technical developments on fuel assembly homogenisation and spent fuel minimisation for in-land water cooled and moderated SMRs. IAEA Interregional Workshop on Technology Development and Applications of Small Modular Reactors (SMRs), hosted by The Government of the Popular Republic of China through the China Atomic Energy Authority. Sanya, Popular Republic of China. September 2023.

International Journals 

N. Silin, A. Fernandez Zuvich, A. Soldati, A. Bevilacqua. Characterization of alumina microspheres produced by combustion torch remelting. Latin American Applied Research 53 No. 4 (2023).

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W. Talavera Ramos, A. Tellería Narváez, L. Dos Santos, A. Bevilacqua, A. Soba, V. Luca. Porous activated carbon monoliths as a novel target material for the production of 99Mo by fission. Journal of Radioanalytical and Nuclear Chemistry 330 (2021) 1299-1310.

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B.S. Jaeckel, A. Bevilacqua, G. Ducros, R. Gauntt, J. Stuckert. Land contamination activity data interpretation from Fukushima Daiichi accident. Nuclear Engineering and Design 300 (2016) 28-33.

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M.O. Prado, N.B. Messi, I.C. Torriani, T.S. Plivelic, A.M. Bevilacqua, M.A. Arribére. The Effect of Radiation on the Density of Glasses. Journal of Non-Crystalline Solids, 289 1-3 (2001) 175-184.

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A.M. Bevilacqua, N.B. Messi de Bernasconi, D.O. Russo, M.A. Audero, M.E. Sterba, A.D. Heredia. Immobilization of simulated high-level liquid wastes in sintered borosilicate, aluminosilicate and aluminoborosilicate glasses. Journal of Nuclear Materials 229 (1996) 187-193.

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A.R. Boccaccini, P.A. Trusty, M.C. Fredel, A.M. Bevilacqua. Effective Fracture Toughness of Brittle Matrix/Ductile Dispersion Composite Materials. Science and Engineering of Composite Materials 4 (3) (1995) 185-190.

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M.A. Audero, A.M. Bevilacqua, N.B. Messi de Bernasconi, Diego O. Russo, M.E. Sterba. Immobilization of simulated high-level wastes in sintered glasses. Journal of Nuclear Materials 223 (1995) 151-156.

IAEA International Conference 

A.M. Bevilacqua, D.H. Caballero, M. Ciávaro, N.I. Grattone, L. Gringauz, D.M. Lysak, R. Mancuso, F.H. Reposi, C.L. Vetere. Spent Fuel, Disused Sources and Radioactive Waste Management Strategy in Argentina. In Radioactive Waste Management: Solutions for a Sustainable Future. Proceedings of an International Conference. Vienna International Centre, Vienna, Austria. November 2021. p. 27-33.

IAEA Technical Documents and Technical Reports 

Demonstrating Performance of Spent Fuel and Related Storage System Components during Very Long Term Storage. Final Report of a Coordinated Research Project. IAEA TECDOC Series. IAEA-TECDOC-1878. IAEA, Vienna, Austria. June 2019.

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Storing Spent Fuel until Transport to Reprocessing or Disposal. IAEA Nuclear Energy Series. No. NF-T-3.3. IAEA, Vienna, Austria. March 2019.

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Hot Cell Post-irradiation Examination and Poolside Inspection of Nuclear Fuel. Proceedings of the IAEA-HOTLAB Technical Meeting held in Smolenice, Slovakia, 23–27 May 2011. IAEA TECDOC Series. IAEA-TECDOC-CD-1693. IAEA, Vienna, Austria. April 2013.

Patent

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InAM · Inorganic nano Advanced Materials SL

Av. Juan López de Peñalver, 21 MÁLAGA, Spain.

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Company Number: ESB56236615 

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