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Materials Science Seminar: Nuclear Thermal Propulsion: Hydrogen Compatibility of Refractory Carbide Fuel (U,Zr)C

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Meeting *Free Food/Drinks Hybrid Seminar

Fri, Mar 6, 2026

1:30 PM – 2:30 PM MST (GMT-7)

MCMR 205 & Zoom

1435 W University Dr, , Boise, ID 83706, United States

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Learn from Dr. Sheng Dai in his talk, "Nuclear Thermal Propulsion: Hydrogen Compatibility of Refractory Carbide Fuel (U,Zr)C".

Light refreshments will be provided.

Abstract:As humanity looks toward crewed missions to Mars and the outer solar system, traditional chemical propulsion systems face limitations in mass efficiency and transit time. Nuclear Thermal Propulsion (NTP), offers a transformative solution by utilizing a fission reactor to heat hydrogen propellant to extreme temperatures. This concept achieves higher thrust and exhaust velocities than those of the most advanced chemical rockets, significantly reducing mission duration and radiation exposure for crew members. Nuclear fuel and core materials in NTP systems face a critical challenge: they must withstand high temperatures (~2600 C) and hydrogen-induced corrosion.

This seminar explores the hydrogen compatibility of refractory carbide fuels, with a specific focus on Uranium-Zirconium Carbide (U,Zr)C. As a solid-solution fuel, (U,Zr)C offers distinct advantages for nuclear thermal propulsion, including a high melting point, high thermal conductivity, and inherent stability in corrosive hydrogen environments. By analyzing recent experimental data on mass loss rates, X-ray diffraction, and microstructural evolution following high-temperature hydrogen exposure in (U,Zr)C, this session evaluates how fuel density and uranium carbide (UC) concentration influence performance. Quantifying the effects of hydrogen corrosion in the fuel is essential for maintaining reactor structural integrity over long-duration missions, providing a foundation for the next generation of deep space exploration vehicles.

Where

MCMR 205 & Zoom

1435 W University Dr, , Boise, ID 83706, United States

Speakers

Jhonathan Rosales's profile photo

Jhonathan Rosales

Nuclear Fuels Lead for the Space Nuclear Propulsion Program

NASA’s Marshall Space Flight Center.



Dr. Jhonathan Rosales serves as the Nuclear Fuels Lead for the Space Nuclear Propulsion Program at NASA’s Marshall Space Flight Center. In this role, he manages a multi-million dollar annual budget and directs a multidisciplinary team of researchers and engineers dedicated to developing advanced nuclear fuels for space applications. His expertise focuses on the fabrication and characterization of nuclear materials, specifically the microstructural evolution and chemical compatibility of high-temperature ceramics, refractory metals, and nuclear fuels under extreme hot hydrogen environments.



Prior to joining NASA, Dr. Rosales served as a Fellow Research Assistant at Idaho National Laboratory, where he contributed to pioneering work in the additive manufacturing of nuclear fuels (U3Si2) and the Advanced Gas Reactor TRISO fuel development program. His research background includes the development of accident-tolerant fuels for light water reactors.

Dr. Rosales holds a Ph.D. and a Master’s degree in Nuclear Engineering from the University of Florida, and a Bachelor of Science in Mathematics from Wisconsin Lutheran College. He is a recipient of the 2020 NASA Early Career Achievement Medal for his technical innovations in nuclear fuels. An active leader in the scientific community, he currently serves on the Executive Committee for the American Nuclear Society’s Aerospace Nuclear Science & Technology Division (2025–2029) and represents the U.S. as an expert to the International Atomic Energy Agency (IAEA) on technology readiness for small modular reactors (SMRs).

 

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