Back to results

Massachusetts Institute of Technology

Increasing Cermet Fuel Thermal Margin with Thoria for Nuclear Thermal Propulsion

Abstract

dc:description.abstract

Nuclear thermal propulsion (NTP) technology was identified as an alternative for faster space travel over chemical combustion propulsion systems by NASA in its Design Reference Addendum 5.0. Potential improvements to NTP performance were considered by improving the fuel margin to melting point. A thorium-dioxide stabilized, high-assay low enriched uranium (HALEU) tungsten-uranium dioxide (W-UO2) CERMET fueled nuclear thermal propulsion (NTP) concept was produced based on the Space Capable Cryogenic Thermal Engine (SCCTE) reactor1. Axial fuel thoria fraction adjustments to improve the fuel thermal margin the reactor’s specific impulse were studied using a one-dimensional axial thermohydraulic analysis of an equivalent annulus model of the average fuel coolant channel. Based on the one-dimensional analysis, fuel composition was adjusted leading to a fuel mass decrease of 5.45 kilograms, excess-reactivity reduction of 962 pcm, and an increased fuel margin to melting point of 740 K for the average fuel. Finally, a three-dimensional computational fluid dynamics (CFD) model of the hottest fuel pin of the base and adjusted designs with neutronics-informed three-dimensional fuel heating rates were compared. The CFD analysis predicted fuel melting in the hottest pin of both designs, identifying the potential need for additional design adjustment outside of fuel composition. The suggested changes reduced the total melting volume by 10 percent. Thus, temperature-informed adjustment of fuel thoria fraction offered improvements in fuel melting point.

Degree

thesis:*
Name thesis:degree_name
Master
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
2023

Author and committee

dc:creator, dc:contributor.*
Author dc:creator
  • Park, Gyutae
Advisor dc:contributor.advisor
  • Shirvan, Koroush

Rights

dc:rights
Statement dc:rights
  • Attribution-NonCommercial-ShareAlike 4.0 International (CC BY-NC-SA 4.0)
  • Copyright retained by author(s)

Identifiers

dc:identifier.*
Handle dc:identifier.uri
https://hdl.handle.net/1721.1/151460
OAI identifier oai:identifier
oai:dspace.mit.edu:1721.1/151460

Chain of custody

source
Harvested from
MIT
Base URL
dspace.mit.edu/oai/request
Last updated
2026-07-22
Source record
OAI-PMH GetRecord
related terms
citation

Park, Gyutae. Increasing Cermet Fuel Thermal Margin with Thoria for Nuclear Thermal Propulsion. Massachusetts Institute of Technology, 2023. https://hdl.handle.net/1721.1/151460