NSUF 25-5332: Neutron Irradiation Damage and Transmutation Products in Diffusion-Bonded 316L SS/B4C

Shielding mass remains one of the most critical constraints in nuclear thermal propulsion system design, driving demand for materials that are both lightweight and capable of withstanding high temperatures, neutron flux, and hydrogen corrosion, thereby necessitating advanced material solutions1. Diffusion-bonded joints of 316L stainless steel with boron carbide offer significant promise for multilayer shielding applications, given their potential for optimized structural integrity and radiation shielding properties. However, the underlying microstructural properties of this material system and bonding scheme under irradiation remain insufficiently explored. This proposal is aimed at using the advanced characterization facilities at The Ohio State University’s Center for Electron Microscopy Analysis, the Michigan Center for Materials Characterization, and the irradiated sample preparation facilities of The Ohio State University’s Nuclear Reactor Laboratory to develop the understanding and nuances of grain boundary migration and shielding capabilities of the material system.

Additional Info

Field Value
Awarded Institution The Ohio State University
DOI 10.46936/NSUF/60015366
Embargo End Date 2027-09-03
Facility Tech Lead Raymond Cao
Irradiation Facilities Ohio State University Research Reactor
NSUF Call FY 2025 RTE 2nd Call
PI Calvin Chandler
PIE Facilities Ohio State University Research Reactor
Project Member Dr. Kevin Field, Associate Professor - University of Michigan (https://orcid.org/0000-0002-3105-076X)
Project Member Mr. Calvin Chandler, Graduate Student and Research Associate - The Ohio State University (https://orcid.org/0000-0002-2939-1645)
Project Member Mr. Timothy DeFranco, Graduate Researcher, P.h.D. Student - University of Michigan
Project Type RTE