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Technical Papers

Evaluation of Non-Oxide Fuel for Fission-Based Nuclear Reactors on Spacecraft

, ORCID Icon, &
Pages 755-765 | Received 15 Jun 2018, Accepted 12 Sep 2018, Published online: 25 Oct 2018

References

  • S. S. VOSS, D. PALAC, and M. GIBSON, “Fission Power Sources for Space and Human Planetary Exploration,” Proc. Nuclear and Emerging Technologies for Space 2018, Las Vegas, Nevada, February 26–March 1, 2018, American Nuclear Society (2018).
  • R. A. JOHNSON, W. T. MORGAN, and S. R. ROCKLIN, “Design, Ground Test and Flight Test of SNAP 10A, First Reactor in Space,” Nucl. Eng. Des., 5, 1, 7 (1967); https://doi.org/10.1016/0029-5493(67)90074-X.
  • M. S. EL-GENK, “Deployment History and Design Considerations for Space Reactor Power Systems,” Acta Astronaut., 64, 9–10, 833 (2009); https://doi.org/10.1016/j.actaastro.2008.12.016.
  • S. J. HOFFMAN and D. I. KAPLAN, “Human Exploration of Mars: The Reference Mission of the NASA Mars Exploration Study Team,” NASA Special Publication 6107, National Aeronautics and Space Administration (1997).
  • R. TAYLOR, “Prometheus Project Final Report,” NASA: 982-R120461, National Aeronautics and Space Administration (2005).
  • R. J. CASSADY et al., “Recent Advances in Nuclear Powered Electric Propulsion for Space Exploration,” Energy Convers. Manage., 49, 3, 412 (2008); https://doi.org/10.1016/j.enconman.2007.10.015.
  • J. ASHCROFT and C. ESHELMAN, “Summary of NR Program Prometheus Efforts,” AIP Conf. Proc., Vol. 880, p. 497, American Institute of Physics (2007).
  • M. J. WOLLMAN and M. J. ZIKA, “Prometheus Project Reactor Module Final Report, For Naval Reactors Information,” SP-67110-0008, Knolls Atomic Power Lab (2006).
  • H. RICKOVER, “Paper Reactors, Real Reactors,” Atomic Energy Committee (1970).
  • M. A. GIBSON et al., “Development of NASA’s Small Fission Power System for Science and Human Exploration,” NASA/TM-2015-218460, National Aeronautics and Space Administration (2015).
  • L. S. MASON, M. A. GIBSON, and D. POSTON, “Kilowatt-Class Fission Power Systems for Science and Human Precursor Missions,” NASA/TM-2013-216541 National Aeronautics and Space Administration (2013).
  • D. PALAC et al., “Nuclear Systems Kilopower Overview,” Proc. Nuclear and Emerging Technologies for Space 2016, Huntsville, Alabama, February 22–25, 2016, American Nuclear Society (2016).
  • M. A. GIBSON et al., “NASA’s Kilopower Reactor Development and the Path to Higher Power Missions,” NASA/TM-2017-219467, National Aeronautics and Space Administration (2017).
  • D. I. POSTON et al., “Design of the KRUSTY Reactor,” Proc. Nuclear and Emerging Technologies for Space 2018, Las Vegas, Nevada, February 26–March 1, 2018, American Nuclear Society (2018).
  • R. J. McCONN et al., “Compendium of Material Composition Data for Radiation Transport Modeling,” PNNL-15870, Rev. 1, Pacific Northwest National Laboratory (2011).
  • A. M. CRONENBERG and W. A. RANKEN, “Irradiation Effects on Fuels for Space Reactors,” LA-UR-84-2651, Los Alamos National Laboratory (1984).
  • T. GOORLEY et al., “Initial MCNP6 Release Overview,” Nucl. Technol., 180, 3, 298 (2012); https://doi.org/10.13182/NT11-135.
  • F. B. BROWN, “The makxsf Code with Doppler Broadening,” LA-UR-06-7002, Los Alamos National Laboratory (2006).
  • J. J. DUDERSTADT and L. J. HAMILTON, Nuclear Reactor Analysis, Vol. 1, Wiley, New York (1976).
  • M. CHADWICK et al., “ENDF/B-VII. 1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data,” Nucl. Data Sheets, 112, 12, 2887 (2011); https://doi.org/10.1016/j.nds.2011.11.002.
  • M. MEYER, R. FIELDING, and J. GAN, “Fuel Development for Gas-Cooled Fast Reactors,” J. Nucl. Mater., 371, 1, 281 (2007); https://doi.org/10.1016/j.jnucmat.2007.05.013.
  • B. FENG et al., “Light Water Breeding with Nitride Fuel,” Prog. Nucl. Energy, 53, 7, 862 (2011); https://doi.org/10.1016/j.pnucene.2011.06.001.
  • J. WALLENIUS, Y. ARAI, and K. MINATO, “Influence of N-15 Enrichment on Neutronics, Costs and C-14 Production in Nitride Fuel Cycle Scenarios,” Proc. Japan Atomic Energy Research Institute (JAERICONF–2004-015), (2004).

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