Lightweight Heat Pipe Radiator for Nuclear Reactor Power Systems on Lunar Surface

References

• M. RUCKER, “Integrated Surface Power Strategy for Mars,” Proc. Nuclear and Emerging Technologies for Space 2015 (NETS), Albuquerque, New Mexico, February 23–26, 2015, American Nuclear Society (2015).
   Google Scholar
• L. KALDON, “Overview of NASA Fission Surface Power,” Proc. Nuclear and Emerging Technologies for Space 2023 (NETS), Idaho Falls, Idaho, May 7–11, 2023, American Nuclear Society (2023).
   Google Scholar
• J. ANGELO JR. and D. BUDEN, Space Nuclear Power, pp. 159–176, Orbit Book Company, Malabar, Florida (1985).
   Google Scholar
• A. MARRIOTT and T. FUJITA, “Evolution of SP-100 System Designs,” AIP Conf. Proc., 301, 157 (1994).
   Google Scholar
• T. M. SCHRIENER and M. S. EL-GENK, “Thermal-Hydraulics and Safety Analyses of the Solid Core-Sectored Compact Reactor (SC-SCoRe) and Power System,” Prog. Nucl. Energy, 76, 216 (2014); http://dx.doi.org/10.1016/j.pnucene.2014.05.020.
   Web of Science ®Google Scholar
• M. S. EL-GENK and J.-M. TOURNIER, “Performance Analysis of Potassium Heat Pipes Radiator for HP-STMCs Space Reactor Power System,” AIP Conf. Proc., 699, 793 (2004).
   Google Scholar
• M. S. EL-GENK and J.-M. TOURNIER, “‘SAIRS’—Scalable AMTEC Integrated Reactor Space Power System,” J. Prog. Nucl. Energy, 45, 25 (2004); http://dx.doi.org/10.1016/j.pnucene.2004.08.002.
   Web of Science ®Google Scholar
• L. MASON, D. POSTON, and L. QUALLS, “System Concepts for Affordable Fission Surface Power,” NASA/TM-2008-215166, NASA Glenn Research Center (2008).
   Google Scholar
• K. L. LEE et al., “Titanium-Water Heat Pipe Radiators for Space Fission Power System Thermal Management,” Microgravity Sci. Technol., 32, 453 (2020); http://dx.doi.org/10.1007/s12217-020-09780-5.
   Web of Science ®Google Scholar
• D. I. POSTON, “The Heat Pipe-Operated Mars Exploration Reactor (HOMER),” AIP Conf. Proc., 552, 797 (2001).
   Google Scholar
• R. HARTY and L. MASON, “100 kWe Lunar/Mars Surface Power Utilizing the SP-100 Reactor with Dynamic Conversion,” AIP Conf. Proc., 271, 1065 (1993).
   Google Scholar
• M. J. WOLLMAN and M. J. ZIKA, “Prometheus Project Reactor Module Final Report,” SPP-67110-0008, Knolls Atomic Power Laboratory and Bettis Atomic Power Laboratory (2006).
   Google Scholar
• J. SIAMIDIS and L. S. MASON, “A Comparison of Coolant Options for Brayton Power Conversion Heat Rejection Systems,” NASA/TM-2006-214121, NASA Glenn Research Center (2006).
   Google Scholar
• J. ELLIOTT et al., “Prometheus—Project Lunar Fission Surface Power System Study Report,” JPL-982-R66153, NASA Jet Propulsion Laboratory (2005).
   Google Scholar
• M. S. EL-GENK, J.-M. TOURNIER, and B. M. GALLO, “Dynamic Simulation of a Space Reactor System with Closed Brayton Cycle Loops,” J. Propul. Power, 26, 3, 394 (2010); http://dx.doi.org/10.2514/1.46262.
   Web of Science ®Google Scholar
• M. S. EL-GENK and J.-M. TOURNIER, “High Temperature Water Heat Pipes Radiator for a Brayton Space Reactor Power System,” AIP Conf. Proc., 813, 716 (2006).
   Google Scholar
• D. I. POSTON, R. J. KAPERNICK, and R. M. GUFFEE, “Design and Analyses of the SAFE-400 Space Fission Reactor,” AIP Conf. Proc., 608, 578 (2002).
   Google Scholar
• M. S. EL-GENK and J.-M. TOURNIER, “Performance Comparison of Potassium and Sodium Vapor Anode, Multi-Tube AMTEC Converters,” J. Energy Convers. Manage., 43, 1931 (2002); http://dx.doi.org/10.1016/S0196-8904(01)00142-X.
   Web of Science ®Google Scholar
• “Space Technology Research Grants Program, Early-Stage Innovations Appendix,” 80HQTR21NOA01-21ESI-B2, NASA Space Technology Mission Directorate (2021).
   Google Scholar
• M. S. EL-GENK et al., “Advanced Lightweight Heat Rejection Radiators for Space Nuclear Power Systems Year 1 ESI Continuation Review Grant Performance Summary,” Technical Report 21 ESI-0049-1, The University of New Mexico Institute for Space and Nuclear Power Studies (2022).
   Google Scholar
• S. A. HATTON and M. S. EL-GENK, “Sectored Compact Space Reactor (SCoRe) Concepts with a Supplementary Lunar Regolith Reflector,” Prog. Nucl. Energy, 51, 93 (2009); http://dx.doi.org/10.1016/j.pnucene.2007.12.003.
   Web of Science ®Google Scholar
• M. S. EL-GENK, “Deployment History and Design Considerations for Space Reactor Power Systems,” Acta Astronaut., 64, 9–10, 833 (2009); http://dx.doi.org/10.1016/j.actaastro.2008.12.016.
   Web of Science ®Google Scholar
• M. S. EL-GENK and T. M. SCHRIENER, “Design and Analyses of Lightweight Radiator Module for Nuclear Reactor Lunar Surface Power,” Proc. AIAA Accelerating Space Commerce, Exploration, and New Discovery (ASCEND 2023), Las Vegas, Nevada, October 23–25, 2023, American Institute of Aeronautics and Astronautics (2023).
   Google Scholar
• M. S. EL-GENK, T. M. SCHRIENER, and O. ANDEROGLU, “Advanced Lightweight Heat Rejection Radiators for Space Nuclear Power Systems Year 2 ESI Continuation Review Grant Performance Summary,” Technical Report 21 ESI-0049-1, The University of New Mexico Institute for Space and Nuclear Power Studies (2023).
   Google Scholar
• STAR-CCM+ website, SIEMENS PLM (2021); https://plm.sw.siemens.com/.
   Google Scholar
• P. G. KLEMENS and D. F. PEDRAZA, “Thermal Conductivity of Graphite in the Basal Plane,” Carbon, 32, 4, 735 (1994); http://dx.doi.org/10.1016/0008-6223(94)90096-5.
   Web of Science ®Google Scholar
• M. GRUJICIC et al., “Hypervelocity Impact Resistance of Reinforced Carbon–Carbon/Carbon–Foam Thermal Protection Systems,” Appl. Surf. Sci., 252, 5035 (2006); http://dx.doi.org/10.1016/j.apsusc.2005.07.047.
   Web of Science ®Google Scholar
• W. H. XIE et al., “High Velocity Impact Tests on High Temperature Carbon-Carbon Composites,” Composites Part B, 98, 30 (2016); http://dx.doi.org/10.1016/j.compositesb.2016.05.031.
   Web of Science ®Google Scholar
• J.-M. TOURNIER and M. S. EL-GENK, “Current Capabilities of ‘HPTAM’ for Modeling High-Temperature Heat Pipes Startup from a Frozen State,” AIP Conf. Proc., 608, 139 (2002).
   Google Scholar
• M. S. EL-GENK and J.-M. TOURNIER, “Challenges and Fundamentals of Modeling Heat Pipes Startup from a Frozen State,” AIP Conf. Proc., 608, 127 (2002).
   Google Scholar
• A. E. SCHEIDEGGER, The Physics of Flow Through Porous Media, 3rd ed., University of Toronto Press, Toronto, Canada (1974).
   Google Scholar
• J.-M. TOURNIER and M. S. EL-GENK, “Transient Analysis of the Startup of a Water Heat Pipe from a Frozen State,” J. Numer. Heat Transfer Part A, 28, 461 (1995); http://dx.doi.org/10.1080/10407789508913756.
   Web of Science ®Google Scholar
• S. V. PATANKAR, Numerical Heat Transfer and Fluid Flow, Hemisphere Publishing Company, Washington, D.C. (1980).
   Google Scholar
• A. M. FAGHRI, M. BUCHKO, and Y. CAO, “A Study of High Temperature Heat Pipes with Multiple Heat Sources and Sinks, Part I: Experimental Methodology and Frozen Startup Profiles,” ASME J. Heat Transfer, 113, 4, 1003 (1991); http://dx.doi.org/10.1115/1.2911193.
   Web of Science ®Google Scholar
• R. S. REID et al., “Heat Pipe Development for Advanced Energy Transport Concepts, Phase II—Progress Report Covering the Period October 1, 1997, to September 30, 1998,” LA-13549-PR, Los Alamos National Laboratory (1999).
   Google Scholar
• R. C. WERNER, E. C. KING, and R. A. TIDBALL, “Heat Transfer with Sodium–Potassium Liquid Alloys,” presented at Annual Meeting of American Institute of Chemical Engineers, Pittsburgh, Pennsylvania, December 5, 1949.
   Google Scholar
• X. CHENG and N. I. TAK, “Investigation on Turbulent Heat Transfer to Lead–Bismuth Eutectic Flows in Circular Tubes of Nuclear Applications,” J. Nucl. Eng. Des., 236, 385 (2006); http://dx.doi.org/10.1016/j.nucengdes.2005.09.006.
   Web of Science ®Google Scholar
• L. CHANDRA et al., “A Stepwise Development and Validation of a RANS Based CFD Modeling Approach for the Hydraulic and Thermal-Hydraulic Analysis of Liquid Metal Flow in a Fuel Assembly,” J. Nucl. Eng. Des., 239, 1988 (2009); http://dx.doi.org/10.1016/j.nucengdes.2009.05.022.
   Web of Science ®Google Scholar
• G. GRÖTZBACH, “Challenges in Low-Prandtl Number Heat Transfer Simulation and Modeling,” J. Nucl. Eng. Des., 264, 41 (2013); http://dx.doi.org/10.1016/j.nucengdes.2012.09.039.
   Web of Science ®Google Scholar
• A. J. REYNOLDS, “The Prediction of Turbulent Prandtl and Schmidt Numbers,” Int. J. Heat Mass Transfer, 18, 1055 (1975); http://dx.doi.org/10.1016/0017-9310(75)90223-9.
   Web of Science ®Google Scholar
• T. M. SCHRIENER and M. S. EL-GENK, “Convection Heat Transfer of NaK-78 Liquid Metal in a Circular Tube and a Tri-Lobe Channel,” Int. J. Heat Mass Transfer, 86, 234 (2015); http://dx.doi.org/10.1016/j.ijheatmasstransfer.2015.02.065.
   Web of Science ®Google Scholar
• V. D. TALANOV and P. A. USHAKOV, “Study of Heat Transfer in Liquid Metals in Round Pipes,” Liquid Metals, pp. 5–7, P. L. KIRILLOV, V. I. SUBBOTIN, and P. A. USHAKOV, Eds., Atomizdat, Moscow (1967).
   Google Scholar
• G. P. PETERSON, An Introduction to Heat Pipes: Modeling, Testing, and Applications, John Wiley & Sons, New York (1994).
   Google Scholar