Preliminary design and assessment of a heat pipe residual heat removal system for the reactor driven subcritical facility |
Zhang, Wenwen
(School of Nuclear Science and Technology, Xi'an Jiaotong University)
Sun, Kaichao (Massachusetts Institute of Technology, Nuclear Reactor Laboratory) Wang, Chenglong (School of Nuclear Science and Technology, Xi'an Jiaotong University) Zhang, Dalin (School of Nuclear Science and Technology, Xi'an Jiaotong University) Tian, Wenxi (School of Nuclear Science and Technology, Xi'an Jiaotong University) Qiu, Suizheng (School of Nuclear Science and Technology, Xi'an Jiaotong University) Su, G.H. (School of Nuclear Science and Technology, Xi'an Jiaotong University) |
1 | S.M. Bragg-Sitton, Analysis of Space Reactor System Components: Investigation through Simulation and Non-nuclear Testing, Diss. University of Michigan, United States, 2004. |
2 | M. Houts, L. Kos, D. Poston, January). Potential operating orbits for fission electric propulsion systems driven by the SAFE-400, in: AIP Conference Proceedings, vol. 608, American Institute of Physics, 2002, pp. 717-721. No. 1. |
3 | M.S. El-Genk, J.M.P. Tournier, "SAIRS"-scalable AMTEC integrated reactor space power system, Prog. Nucl. Energy 45 (1) (2004) 25-69. DOI |
4 | A. Bushman, et al., The Martian Surface Reactor: an Advanced Nuclear Power Station for Manned Extraterrestrial Exploration, MIT-NSA-TR-003, 2004. |
5 | A. Maioli, et al., Modernization of Technical Requirements for Licensing of Advanced Non-light Water Reactors Westinghouse eVinciTM Micro-reactor Licensing Modernization Project Demonstration, Southern Company, United States, 2019. |
6 | T.H. Newton Jr., M.S. Kazimi, E.E. Pilat, Development of a low-enricheduranium core for the MIT reactor, Nucl. Sci. Eng. 157 (3) (2007) 264-279. DOI |
7 | Z.J. Zuo, A. Faghri, A network thermodynamic analysis of the heat pipe, Int. J. Heat Mass Tran. 41 (11) (1998) 1473-1484. DOI |
8 | M.A. Gibson, L.S. Mason, C.L. Bowman, D.I. Poston, P.R. McClure, J. Creasy, C. Robinson, Development of NASA's Small Fission Power System for Science and Human Exploration, 2015. |
9 | J.D. Bess, A Basic LEGO Reactor Design for the Provision of Lunar Surface Power. No. INL/CON-08-14353, Idaho National Laboratory, United States, 2008. |
10 | D.I. Poston, The heatpipe-operated Mars exploration reactor (HOMER), AIP Conference Proceedings 552 (2001). No. 1. AIP. |
11 | E. Greenspan, Solid Core Heat-Pipe Nuclear Battery Type Reactor, University of California, United States, 2008. No. DOE/ID/14706). |
12 | A. Faghri, Heat pipes: review, opportunities and challenges, Frontiers in Heat Pipes (FHP) 5 (1) (2014). |
13 | N.R. Brown, B.R. Betzler, J.J. Carbajo, A.J. Wysocki, M.S. Greenwood, C. Gentry, A.L. Qualls, Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: core design and safety analysis, Ann. Nucl. Energy 103 (2017) 49-59. DOI |
14 | A.L. Qualls, B.R. Betzler, N.R. Brown, J.J. Carbajo, M.S. Greenwood, R. Hale, A.J. Wysocki, Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: motivation and overview, Ann. Nucl. Energy 107 (2017) 144-155. DOI |
15 | R.R. Romatoski, L.W. Hu, Fluoride-salt-cooled high-temperature test reactor thermal-hydraulic licensing and uncertainty propagation analysis, Nucl. Technol. 205 (11) (2019) 1495-1512. DOI |
16 | K. Sun, L.W. Hu, C. Forsberg, Neutronics feasibility of an MIT reactor-driven subcritical facility for the fluoride-salt-cooled high-temperature reactor, Int. J. Energy Res. 41 (14) (2017) 2248-2257. DOI |
17 | W. Zhang, D. Zhang, W. Tian, S. Qiu, G.H. Su, Thermal-hydraulic analysis of the improved TOPAZ-II power system using a heat pipe radiator, Nucl. Eng. Des. 307 (2016) 218-233. DOI |
18 | V. Gnielinski, New equations for heat and mass transfer in turbulent pipe and channel flow, Int. Chem. Eng. 16 (2) (1976) 359-368. |
19 | D. Taler, Experimental determination of correlations for mean heat transfer coefficients in plate fin and tube heat exchangers, Arch. Therm. 33 (2012) 3-26. |
20 | K. Sun, L.W. Hu, C. Forsberg, Neutronic design features of a transportable fluoride-salt-cooled high-temperature reactor, J. Nucl. Eng. Radiat. Sci. 2 (3) (2016). |