Evaluation of Non-Oxide Fuel for Fission-based Nuclear Reactors on Spacecraft
Abstract
The goal of this project was to study the performance of atypical uranium-based fuels in a nuclear reactor capable of producing 1 megawatt of thermal power with a 15-year core life for space-based applications. Specifically, the project investigated the use of uranium molybdenum (UMo), uranium nitride (UN), or uranium carbide (UC) and compared their performance to uranium oxide (UO2) which is the fuel form used in the vast majority of commercial nuclear reactor applications. These alternative fuels have improved thermal conductivity and higher uranium loading density as compared to UO2. Improved thermal conductivity of the fuel allows a design with lower peak core temperatures thereby reducing the chance of violating thermal limits of core materials. Fuel with higher uranium loading density can have more of the fissile uranium-235 isotope present per unit of volume. This allows a design with a smaller and potentially lighter core, which is a significant advantage. The results of this study indicate that use of both UC and UN may result in significant weight savings due to higher uranium loading density.
Document Details
- Document Type
- Technical Report
- Publication Date
- May 21, 2018
- Accession Number
- AD1054386
Entities
People
- Dakota J. Allen
Organizations
- United States Naval Academy