Effects of heat treatment on U–Mo fuel foils with a zirconium diffusion barrier

Journal Article · 01 May 2015 · Journal of Nuclear Materials

DOI: https://doi.org/10.1016/j.jnucmat.2015.02.017 · OSTI ID:1252359

Jue, Jan-Fong; Trowbridge, Tammy L.; Breckenridge, Cynthia R.; Moore, Glenn A.; Meyer, Mitchell K.; Keiser, Jr., Dennis D.

• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA); USDOE Office of Nuclear Energy (NE)
• Grant/Contract Number: NA-212; AC07-05ID14517
• OSTI ID: 1252359
• Journal Information: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 460 Journal Issue: C; ISSN 0022-3115
• Publisher: ElsevierCopyright Statement
• Country of Publication: Netherlands
• Language: English