Synthesis and oxidation behavior of Cr alloyed uranium borides at high temperatures

Following the nuclear accident at Fukushima Daiichi Power Station in 2011, an urgent need for safer, more economical, and versatile nuclear fuels has arisen. In recent years, uranium boride (as a tetraboride and diboride) has been further investigated as a candidate fuel form for its high thermal conductivity, high melting point, high uranium loading, and potential for dual use as a fuel and burnable absorber. In this work, the synthesis, structural behavior, and oxidation behavior of uranium borides and chromium- and yttrium- alloyed uranium borides are investigated. The structure of the synthesized uranium borides and chromium- and yttrium- alloyed uranium borides were probed using synchrotron X- ray Powder Diffraction (XRD) and Pair Distribution Function (PDF) analysis with in-situ heating. The methods and challenges in synthesizing uranium boride and chromium- and yttrium-alloyed uranium boride, as well as the consequential thermophysical and oxidation properties of these potential fuel forms, are elucidated in this work.

Name thesis:degree_name

Bachelor

Department dc:contributor.department

Massachusetts Institute of Technology. Department of Nuclear Science and Engineering

Grantor dc:publisher

Massachusetts Institute of Technology

Year dc:date.issued

2025

Author dc:creator

• Moeykens, Riley S.

Advisor dc:contributor.advisor

• Jossou, Ericmoore

Statement dc:rights

• In Copyright - Educational Use Permitted
• Copyright retained by author(s)

Licence dc:rights.uri

• https://rightsstatements.org/page/InC-EDU/1.0/

Handle dc:identifier.uri

https://hdl.handle.net/1721.1/162078

OAI identifier oai:identifier

oai:dspace.mit.edu:1721.1/162078