DOI QR코드

DOI QR Code

INNOVATIVE CONCEPT FOR AN ULTRA-SMALL NUCLEAR THERMAL ROCKET UTILIZING A NEW MODERATED REACTOR

  • NAM, SEUNG HYUN (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology) ;
  • VENNERI, PAOLO (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology) ;
  • KIM, YONGHEE (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology) ;
  • LEE, JEONG IK (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology) ;
  • CHANG, SOON HEUNG (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology) ;
  • JEONG, YONG HOON (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology)
  • Received : 2014.12.17
  • Accepted : 2015.06.06
  • Published : 2015.12.25

Abstract

Although the harsh space environment imposes many severe challenges to space pioneers, space exploration is a realistic and profitable goal for long-term humanity survival. One of the viable and promising options to overcome the harsh environment of space is nuclear propulsion. Particularly, the Nuclear Thermal Rocket (NTR) is a leading candidate for nearterm human missions to Mars and beyond due to its relatively high thrust and efficiency. Traditional NTR designs use typically high power reactors with fast or epithermal neutron spectrums to simplify core design and to maximize thrust. In parallel there are a series of new NTR designs with lower thrust and higher efficiency, designed to enhance mission versatility and safety through the use of redundant engines (when used in a clustered engine arrangement) for future commercialization. This paper proposes a new NTR design of the second design philosophy, Korea Advanced NUclear Thermal Engine Rocket (KANUTER), for future space applications. The KANUTER consists of an Extremely High Temperature Gas cooled Reactor (EHTGR) utilizing hydrogen propellant, a propulsion system, and an optional electricity generation system to provide propulsion as well as electricity generation. The innovatively small engine has the characteristics of high efficiency, being compact and lightweight, and bimodal capability. The notable characteristics result from the moderated EHTGR design, uniquely utilizing the integrated fuel element with an ultra heat-resistant carbide fuel, an efficient metal hydride moderator, protectively cooling channels and an individual pressure tube in an all-in-one package. The EHTGR can be bimodally operated in a propulsion mode of $100MW_{th}$ and an electricity generation mode of $100MW_{th}$, equipped with a dynamic energy conversion system. To investigate the design features of the new reactor and to estimate referential engine performance, a preliminary design study in terms of neutronics and thermohydraulics was carried out. The result indicates that the innovative design has great potential for high propellant efficiency and thrust-to-weight of engine ratio, compared with the existing NTR designs. However, the build-up of fission products in fuel has a significant impact on the bimodal operation of the moderated reactor such as xenon-induced dead time. This issue can be overcome by building in excess reactivity and control margin for the reactor design.

Keywords

Acknowledgement

Supported by : National research Foundation of Korea (NFR)

References

  1. S. Gunn, Nuclear propulsion - a historical perspective, Space Policy 17 (2001) 291-298. https://doi.org/10.1016/S0265-9646(01)00044-3
  2. P.M. Sforza, M.L. Shooman, D.G. Pelaccio, A safety and reliability analysis for space nuclear thermal propulsion systems, Acta Astronaut. 30 (1993) 67-83. https://doi.org/10.1016/0094-5765(93)90101-2
  3. S.H. Nam, S.H. Chang, To Mars and beyond with nuclear power - design concept of Korea advanced nuclear thermal engine rocket, in: Transactions of the Korean Nuclear Society Spring Meeting, KNS, Gwangju, Korea, 2013.
  4. R.H. Frisbee, Advanced space propulsion for the 21st century, J. Propul. Power 19 (2003) 1129-1154. https://doi.org/10.2514/2.6948
  5. F.J. Dyson, Death of a project, Science 149 (1965) 141-144. https://doi.org/10.1126/science.149.3680.141
  6. B.P. Bromley [Internet]. Nuclear propulsion: getting more miles per gallon, Astrodigital. (2000), Available from: http://www.astrodigital.org/space/nuclear.html.
  7. E.S. Pedersen, Chapter 6. Nuclear Rocket Engine Design, in: C.W. Besserer, F.E. Nixon (Eds.), Nuclear Energy in Space, Prentice-Hall, Inc., Englewood Cliffs, NJ, USA, 1964, pp. 184-252.
  8. S.K. Borowski, D.R. McCurdy, T.W. Packard, Nuclear thermal propulsion (NTP): a proven growth technology for human NEO/Mars exploration missions, in: IEEE Aerospace Conference Proceedings, 2012, http://dx.doi.org/10.1109/AERO.2012.6187301.
  9. S.K. Borowski, Nuclear thermal rocket propulsion for future human exploration missions, in: Future In-space Operations (FISO) Colloquium, NASA Glenn Research Center, 2012.
  10. J. Finseth, Overview of Rover Engine Tests - Final Report, NASA-CR-184270, 1991.
  11. B. Schnitzler, S. Borowski, J. Fittje, A 25,000-lbf thrust engine options based on the small nuclear rocket engine design, in: 45th AIAA/ASME/SAE/ASEE Joint Propulsion Conference & Exhibit, AIAA, 2009, pp. 1-8, http://dx.doi.org/10.2514/6.2009-5239. Denver, CO, USA.
  12. S. Borowski, D. McCurdy, T. Packard, Nuclear thermal rocket/vehicle characteristics and sensitivity trades for NASA's Mars design reference architecture (DRA) 5.0 study, in: Proceedings of Nuclear and Emerging Technologies for Space (NETS-2009), ANS, Atlanta, GA, USA, 2009.
  13. H. Ludewig, J.R. Powell, M. Todosow, G. Maise, R. Barletta, D.G. Schweitzer, Design of particle bed reactors for the space nuclear thermal propulsion program, Prog. Nucl. Energy 30 (1996) 1-65. https://doi.org/10.1016/0149-1970(95)00080-4
  14. J.C. Paniagua, J.R. Powell, G. Malse, Design and development of the MITEE-B Bi-Modal nuclear propulsion engine, in: Space Technology and Applications International Forum (STAIF 2003), AIP, Albuquerque, NM, USA, 2003, pp. 438-444.
  15. S. Anghaie, T. Knight, R. Gouw, E. Furman, Square lattice honeycomb Tri-carbide fuels for 50 to 250 KN variable thrust NTP design, in: Space Technology and Applications International Forum (STAIF 2001), AIP, Albuquerque, NM, USA, 2001, pp. 828-836.
  16. S.H. Nam, K.Y. Suh, Conceptual Design of Thermal Engine Rocket Adventurer for Space Nuclear Application, Seoul National University, 2009.
  17. J. Paniagua, G. Maise, J. Powell, Converting the ISS to an Earth-Moon transport system using nuclear thermal propulsion, in: Space Technology and Applications International Forum (STAIF 2008), AIP, Albuquerque, NM, USA, 2008, pp. 492-502.
  18. J. Powell, G. Maise, H. Ludewig, M. Todosow, Highperformance ultra-light nuclear rockets for near-Earth objects interaction missions, Ann. N. Y. Acad. Sci. 822 (1997) 447-467. https://doi.org/10.1111/j.1749-6632.1997.tb48360.x
  19. S. Anghaie, T.W. Knight, J. Plancher, R. Gouw, Development of a Robust Tri-carbide Fueled Reactor for Multi-megawatt Space Power and Propulsion Applications, Innovative Nuclear Space Power and Propulsion Institute (INSPI), University of Florida, Gainesville, FL, USA, 2004.
  20. D. Burkes, D. Wachs, J. Werner, S. Howe, An overview of current and past W-UO2 CERMET fuel fabrication technology, in: Proceedings of Space Nuclear Conference 2007, INL, 2007, pp. 207-216. Boston, MA, USA.
  21. B. Panda, R.R. Hickman, S. Shah, Solid solution carbides are the key fuels for future nuclear thermal propulsion, in: Joint Army-Navy-NASA-Air Force, NASA, Monterey, CA, USA, 2005.
  22. D. Culver, V. Kolganov, R. Rochow, Low thrust, deep throttling, US/CIS integrated NTRE, in: Space Nuclear Power and Propulsion: Eleventh Symposium, AIP, Albuquerque, NM, USA, 1994, pp. 637-651.
  23. E. Furman, S. Anghaie, Thermal hydraulic design analysis of ternary carbide fueled square-lattice honeycomb nuclear rocket engine, in: Space Technology and Applications International Forum (STAIF 1999), AIP, Albuquerque, NM, USA, 1999.
  24. T.W. Knight, S. Anghaie, Processing and fabrication of mixed uranium/refractory metal carbide fuels with liquid-phase sintering, J. Nucl. Mater. 306 (2002) 54-60. https://doi.org/10.1016/S0022-3115(02)01143-1
  25. L. Manocha, High performance carbon-carbon composites, Sadhana 28 (2003) 349-358. https://doi.org/10.1007/BF02717143
  26. S. Yamanaka, K. Yamada, K. Kurosaki, M. Uno, K. Takeda, H. Anada, T. Matsuda, S. Kobayashi, Characteristics of zirconium hydride and deuteride, J. Alloys Compd. 330-332 (2002) 99-104. https://doi.org/10.1016/S0925-8388(01)01448-7
  27. A.J. Stonehouse, Physics and chemistry of beryllium, J. Vac. Sci. Technol. A 4 (1986) 1163. https://doi.org/10.1116/1.573431
  28. R. Smith, J. Miser, Compilation of the Properties of Lithium Hydride, NASA-TM-X-483, DC, USA, 1963.
  29. IAEA, IAEA Nuclear Data Services, 2013.
  30. R. Haslett, Space Nuclear Thermal Propulsion Program e Final Report, Grumman Aerospace Corporation, PL-TR-95-1064, NY, USA, 1995.
  31. S. Locke, R. Ahearn, Material design concepts for uncooled nuclear rocket nozzles, Mater. Sci. Res. (1965) 287-310.
  32. G.L. Bennett, R.J. Hemler, A. Schock, Status report on the U.S. space nuclear program, Acta Astronaut. 38 (1996) 551-560. https://doi.org/10.1016/0094-5765(96)00038-0
  33. L.S. Mason, A comparison of brayton and stirling space nuclear power systems for power levels from 1 kilowatt to 10 megawatts, in: Space Technology and Applications International Forum (STAIF 2001), AIP, Albuquerque, NM, USA, 2001, pp. 1017-1022.
  34. A.K. Hyder, R.L. Wiley, G. Halpert, D.F. Flood, S. Sabripour, Chapter 7. Dynamic energy conversion, in: Spacecraft Power Technologies, Imperial College Press, London, UK, 2000, pp. 323-351.
  35. H. Haller, Analysis of a Double Fin-Tube Flat Condenser-Radiator and Comparison with a Central Fin-Tube Radiator, NASA-TN-D-2558, 1964.
  36. J. Powell, G. Maise, J. Paniagua, SUSEE - Ultra light nuclear space power using the steam cycle, in: 2003 IEEE Aerospace Conference Proceedings, vol. 1, IEEE, Big Sky, MT, USA, 2003, pp. 491-507.
  37. K.A. White, Liquid Droplet Radiator Development Status, NASA-TM-89852, 1987.
  38. NIST, NIST Reference Fluid Thermodynamic and Transport Properties Database (REFPROP), 2010.
  39. S. Gordon, B.J. Mcbride, Computer Program for Calculation of Complex Chemical Equilibrium Compositions and Applications, NASA/RP-1311, 1994.
  40. S.H. Nam, J. Young Choi, P.F. Venneri, Y.H. Jeong, S.H. Chang, Thermohydraulic design analysis modeling for Korea advanced nuclear thermal engine rocket for space application, in: Transactions of the Korean Nuclear Society Spring Meeting, KNS, Jeju, Korea, 2015.
  41. X-5 Monte Carlo Team, MCNP - A General Monte Carlo NParticle Transport Code, Version 5, 836, 2003.
  42. J. Leppanen, Serpent - A Continuous-Energy Monte Carlo Reactor Physics Burnup Calculation Code, VTT Technical Research Centre of Finland, 2013.
  43. P. Venneri, S.H. Nam, Y. Kim, Neutronics study of KANUTER space propulsion reactor, in: Transactions of the Korean Nuclear Society Spring Meeting, KNS, Jeju, Korea, 2014.
  44. R.E. Hyland, Reactor-Weight Study of Beryllium Oxide, Beryllium, Lithium-7 Hydride, and Water as Moderators with Tungsten184 Structural Material and Uranium Dioxide Fuel, NASA-TN-D-1407, 1962.
  45. P. Venneri, P. Husemeyer, W. Deason, G. Rosaire, S. Howe, Y. Kim, Nuclear thermal rocket design using LEU tungsten fuel, in: Transactions of the Korean Nuclear Society Fall Meeting, KNS, Gyeongju, Korea, 2013.
  46. ANSYS Inc, ANSYS CFX Tutorials, 15317, 2010.
  47. S.H. Nam, J.I. Lee, S.H. Chang, Preliminary thermo-hydraulic core design analysis of Korea advanced nuclear thermal engine rocket for space application, in: Transactions of the Korean Nuclear Society Spring Meeting, KNS, Jeju, Korea, 2014.
  48. P. Venneri, Y. Kim, Low enriched uranium fuels in NERVA type nuclear thermal rockets, in: Transactions of the American Nuclear Society, ANS, DC, USA, 2013, pp. 40-41.

Cited by

  1. Modeling Loss-of-Flow Accidents and Their Impact on Radiation Heat Transfer vol.2017, pp.None, 2015, https://doi.org/10.1155/2017/1345938
  2. Passive Reactivity Control of Nuclear Thermal Propulsion Reactors vol.197, pp.1, 2015, https://doi.org/10.13182/nt16-80
  3. Analysis of the Flow Distribution in a Particle Bed Reactor for Nuclear Thermal Propulsion vol.12, pp.19, 2015, https://doi.org/10.3390/en12193590
  4. Numerical Investigation and Parametric Study on Thermal-Hydraulic Characteristics of Particle Bed Reactors for Nuclear Thermal Propulsion vol.206, pp.8, 2015, https://doi.org/10.1080/00295450.2020.1760703
  5. A neutronics optimization approach for preliminary design and safety of nuclear reactors for nuclear thermal propulsion vol.143, pp.None, 2022, https://doi.org/10.1016/j.pnucene.2021.104035