Skip to main navigation Skip to search Skip to main content

Hot hydrogen testing & cermet materials development supporting nuclear thermal propulsion

  • Joseph D. Elkins
  • , Kelsa M. Benensky
  • , Dennis Tucker
  • , Marvin W. Barnes

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Abstract

To significantly reduce travel time and generally increase mission architecture flexibility, crewed missions to Mars and beyond may choose to use nuclear thermal rockets, as they represent a key technological advancement over traditional chemical rockets. Rocket efficiency is measured in terms of specific impulse (Isp) with units of seconds; and nuclear rockets are expected to be capable of 100% increase in Isp as compared to chemical rockets, stemming from the greater energies released in nuclear fission as compared to that available when breaking chemical bonds in combustion. A critical step in the development of nuclear thermal propulsion (NTP) technology is creating nuclear fuel material with key characteristics, such as, low neutron cross sections, a high melting temperature, chemical compatibility with hydrogen propellant, and desirable thermomechanical properties over a wide range of engine operating temperatures. To accomplish this, the reactor’s uranium dioxide fuel particles, which can undergo reduction when exposed to hydrogen near the intended operating temperatures, are suspended within tungsten which is chemically compatible with hydrogen. This is known as a ceramic-metallic (CERMET) fuel of tungsten-coated uranium dioxide, and this research aims to manufacture and test subscale CERMET fuel using zirconium dioxide as a surrogate for uranium dioxide. To optimize the fuel sample microstructures prior to sintering, the larger zirconium dioxide particles are coated with approximately micron-sized tungsten particles using a polyethylene binder. The coating process was optimized by varying the weight percentage of the added binder. The resulting powder mixtures showing the best coating characteristics are then consolidated into a puck-shaped disk by direct current sintering. Both optimized and non-optimized specimens were tested in a hot hydrogen environment using the compact fuel element environmental test (CFEET) located at NASA/Marshall Space Flight Center in the Material and Processes Laboratory. Samples were tested in CFEET at temperatures exceeding 2,000°C in a pure hydrogen environment. Mass loss was determined and the microstructure assessed before and after testing.

Original languageEnglish
Title of host publicationNuclear and Emerging Technologies for Space, NETS 2018
PublisherAmerican Nuclear Society
Pages129-133
Number of pages5
ISBN (Print)9781510859609
StatePublished - 2016
EventNuclear and Emerging Technologies for Space, NETS 2018 - Las Vegas, United States
Duration: Feb 26 2018Mar 1 2018

Publication series

NameNuclear and Emerging Technologies for Space, NETS 2018

Conference

ConferenceNuclear and Emerging Technologies for Space, NETS 2018
Country/TerritoryUnited States
CityLas Vegas
Period02/26/1803/1/18

Keywords

  • CERMET
  • Fuel Material
  • Nuclear Thermal Propulsion
  • Plasma Sintering
  • Tungsten
  • UO2

Fingerprint

Dive into the research topics of 'Hot hydrogen testing & cermet materials development supporting nuclear thermal propulsion'. Together they form a unique fingerprint.

Cite this