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Microscopic analysis of irradiated UN–Mo–W for space nuclear propulsion

Journal Article · · Nuclear Engineering and Design
 [1];  [2];  [2];  [3];  [2];  [4];  [5]
  1. Univ. of Idaho, Idaho Falls, ID (United States); Idaho National Laboratory (INL), Idaho Falls, ID (United States)
  2. Idaho National Laboratory (INL), Idaho Falls, ID (United States)
  3. Idaho National Laboratory (INL), Idaho Falls, ID (United States); National Renewable Energy Laboratory (NREL), Golden, CO (United States)
  4. Univ. of Idaho, Idaho Falls, ID (United States)
  5. Idaho National Laboratory (INL), Idaho Falls, ID (United States); Universities Space Research Association (USRA), Idaho Falls, ID (United States). Center for Space Nuclear Research (CSNR)
Nuclear propulsion is an effective method of providing thrust in deep space, allowing for shorter mission duration for long-term surface missions to Mars. The fuel for nuclear propulsion systems must exhibit superior mechanical and thermal properties, to decrease the possibility of fuel failure and to increase reactor efficiency. Here, the objective of the Sirius project is to fabricate and irradiate cermet fuels at the Idaho National Laboratory Transient Reactor Facility to determine the properties of the fuel after irradiation at prototypical nuclear propulsion start-up conditions. The Sirius project featured 3 test capsules, Sirius-1 featured uranium nitride fuel dispersed in a matrix of tungsten and rhenium, while Sirius-2A and -2B featured uranium nitride-molybdenum-tungsten fuel (UN-Mo-W). The fuel samples from the Sirius-2A and -2B capsules were examined after irradiation using optical microscopy, scanning electron microscopy, and X-ray diffraction analyses. The mechanical properties of the fuel from Sirius-2A and -2B are discussed in a previous work. In this study, the results of the optical microscopy, scanning electron microscopy, and X-ray diffraction analyses are discussed.
Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
National Aeronautics and Space Administration (NASA); USDOE Office of Nuclear Energy (NE)
Grant/Contract Number:
AC07-05ID14517
OSTI ID:
3013360
Report Number(s):
INL/JOU--24-82566
Journal Information:
Nuclear Engineering and Design, Journal Name: Nuclear Engineering and Design Journal Issue: A Vol. 446; ISSN 0029-5493
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

References (10)

Review and Preliminary Investigation into Fuel Loss from Cermets Composed of Uranium Nitride and a Molybdenum-Tungsten Alloy for Nuclear Thermal Propulsion Using Mesoscale Simulations journal September 2021
Equilibrium oxygen partial pressure and phase diagram of the uranium-oxygen system in the composition range between 844 and 1371 K journal November 1984
Ceramics as nuclear reactor fuels journal September 1975
Nuclear propulsion—a historical perspective journal November 2001
Post-irradiation examination of the Sirius-1 nuclear thermal propulsion fuel test journal November 2023
Safe radioisotope thermoelectric generators and heat sources for space applications journal July 2008
Post-irradiation examination of UN-Mo-W fuels for space nuclear propulsion journal January 2025
Assessment of near-term fuel screening and qualification needs for nuclear thermal propulsion systems journal October 2020
Fabrication of UN-Mo CERMET Nuclear Fuel Using Advanced Manufacturing Techniques journal December 2020
Impact of Accident-Tolerant Fuels and Claddings on the Overall Fuel Cycle: A Preliminary Systems Analysis journal November 2014

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