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  5. Fabrication, Thermophysical, and Mechanical Properties of Cermet and Cercer Fuel Composites for Nuclear Thermal Propulsion
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Fabrication, Thermophysical, and Mechanical Properties of Cermet and Cercer Fuel Composites for Nuclear Thermal Propulsion

Date Issued
December 1, 2022
Author(s)
Gaffin, Neal D
Advisor(s)
Steven J. Zinkle
Additional Advisor(s)
Steven J. Zinkle, Lawrence H. Heilbronn, Kelsa Palomares, Justin Milner
Permanent URI
https://trace.tennessee.edu/handle/20.500.14382/28914
Abstract

Nuclear thermal propulsion (NTP) utilizes nuclear fission to double the efficiency of
in-space propulsion systems compared with traditional combustion rocket systems.
NTP systems are limited primarily by the fuel material choice, due to the extreme
conditions they will need to endure, including temperatures up to 3000 K, multiple
thermal cycles with rapid heating and cooling, exposure to hot flowing hydrogen,
large thermal gradients, and high neutron flux. Particle based fuels, namely ceramic-
metallic (cermet) and ceramic-ceramic (cercer) composites are both promising fuel
element material candidates for NTP. Given the high temperature nature, these
materials are difficult to fabricate and very little thermophysical and mechanical
property data exists. The fabrication of a cermet with a molybdenum-tungsten matrix
and a cercer with a zirconium carbide matrix using surrogate fuel particles have been
optimized utilizing spark plasma sintering to produce materials > 97% theoretical
density. Thermophysical properties including the coefficient of thermal expansion,
thermal conductivity, and heat capacity were determined up to 1000 °C. Compression
and notched bend bar tests up to 800 °C also provided information on the effect of
the particles to the strength of the composites. From this data, predictive models
were created to approximate the thermophysical and mechanical properties of fueled
materials for use in NTP design.

Subjects

Nuclear thermal propu...

spark plasma sinterin...

ceramic-metallic (cer...

ceramic-ceramic (cerc...

mechanical testing

Disciplines
Ceramic Materials
Mechanics of Materials
Metallurgy
Other Materials Science and Engineering
Propulsion and Power
Structural Materials
Degree
Doctor of Philosophy
Major
Nuclear Engineering
Comments

I have made a few additional changes (mostly typos). The formatting should still be in accordance with the formatting guidelines. Once accepted, this version is ready to be submitted.

Embargo Date
December 15, 2023
File(s)
Thumbnail Image
Name

Gaffin_Dissertation.docx

Size

29.99 MB

Format

Microsoft Word XML

Checksum (MD5)

928bb5531fdda20ac6a133908f3dec65

Thumbnail Image
Name

Gaffin_Dissertation.pdf

Size

269.63 MB

Format

Adobe PDF

Checksum (MD5)

da92b1176c56d2e461c50f85d7a827af

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