Fission gas retention of densely packed uranium carbonitride tristructural-isotropic fuel particles in a 3D printed SiC matrix-Reference-Cited by-同舟云学术

Fission gas retention of densely packed uranium carbonitride tristructural-isotropic fuel particles in a 3D printed SiC matrix

Published:2023-07 Issue: Volume:580 Page:154419
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Petrie Christian M.^ORCID,Linton Kory D.,Vasudevamurthy Gokul^ORCID,Schappel Danny,Seibert Rachel L.^ORCID,Carpenter David,Nelson Andrew T.^ORCID,Terrani Kurt A.^ORCID

Funder

U.S. Department of Energy

Office of Nuclear Energy

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference60 articles.

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