참고문헌
- R.C. Ewing, Long-term storage of spent nuclear fuels, Nat. Mater. 14 (2015) 252-257. https://doi.org/10.1038/nmat4226
- C. Braun, R. Forrest, Considerations regarding ROK spent nuclear fuel management options, Nucl. Eng. Technol. 45 (2013) 427-438. https://doi.org/10.5516/NET.06.2013.708
- C.E. Till, Y.I. Chang, Plentiful Energy: the Story of the Integral Fast Reactor, Create Space Independent Publishing Platform, 2011.
- H.-S. Lee, G.-I. Park, K.-H. Kang, J.-M. Hur, J.-G. Kim, D.-H. Ahn, Y.-Z. Cho, E.-H. Kim, Pyroprocessing technology development at KAERI, Nucl. Eng. Technol. 43 (2011) 317-328. https://doi.org/10.5516/NET.2011.43.4.317
- T. Inoue, L. Koch, Development of pyroprocessing and its future direction, Nucl. Eng. Technol. 40 (2008) 183-190. https://doi.org/10.5516/NET.2008.40.3.183
-
I.S. Kim, S.C. Oh, H.S. Lim, J.M. Hur, H.S. Lee, Distillation of LiCl from the
$LiCl-Li_2O$ molten salt of the electrolytic reduction process, J. Radioanal. Nucl. Chem. 295 (2013) 1413-1417. https://doi.org/10.1007/s10967-012-1997-2 - J.-H. Lee, Y.-H. Kang, S.-C. Hwang, J.-B. Shim, B.-G. Ahn, E.-H. Kim, S.-W. Park, Electrodeposition characteristics of uranium in molten LiCl-KCl eutectic and its salt distillation behavior, J. Nucl. Sci. Technol. 43 (2006) 263-269. https://doi.org/10.1080/18811248.2006.9711088
- E.-Y. Choi, M.K. Jeon, J.-M. Hur, Reoxidation of uranium in electrochemically reduced simulated oxide fuel during residual salt distillation, J. Radioanal. Nucl. Chem. 314 (2017) 207-213. https://doi.org/10.1007/s10967-017-5404-x
- C.P. Wang, Z.S. Li, W. Fang, X.J. Liu, Thermodynamic database and the phase diagrams of the (U, Th, Pu)-X binary system, J. Phase Equilibria Diffusion 30 (2009) 535-552. https://doi.org/10.1007/s11669-009-9562-6
- S.-W. Kim, J.-M. Hur, D.H. Heo, S.-S. Hong, E.-Y. Choi, Residual salt separation of reaction products in pyroprocessing, in: Korean Radioactive Waste Society 2017 Fall Meeting, Oct. 18-20, 2017. Changwon, Republic of Korea.
-
G.J. Janz, S.W. Lurie, G.L. Gardner, Viscosity of molten
$LiNO_3$ , J. Chem. Eng. Data 23 (1978) 14-16. https://doi.org/10.1021/je60076a003 - M. Wakao, K. Minami, A. Nagashima, Viscosity measurements of molten LiCl in the temperature rage 886-1275K, Int. J. Thermophys. 12 (1991) 223-230. https://doi.org/10.1007/BF00500748
- J.-Y. Kim, S.-E. Bae, D.-H. Kim, Y.S. Choi, J.-W. Yeon, K. Song, High-temperature viscosity measurement of LiCl-KCl molten salts comprising actinides and lanthanides, Bull. Kor. Chem. Soc. 33 (2012) 3871-3874. https://doi.org/10.5012/bkcs.2012.33.11.3871
- S.-C. Jeon, J.-W. Lee, J.-Y. Yoon, Y.-Z. Cho, Scaling up fabrication of UO2 porous pellets with a simulated fuel composition, J. Nucl. Fuel Cycle Waste Technol. 15 (2017) 343-353. https://doi.org/10.7733/jnfcwt.2017.15.4.343
-
E.-Y. Choi, J.-K. Kim, H.-S. Im, I.-K. Choi, S.-H. Na, J.W. Lee, S.M. Jeong, J.-M. Hur, Effect of the
$UO_2$ form on the electrochemical reduction rate in a$LiCl-Li_2O$ molten salt, J. Nucl. Mater. 437 (2013) 178-187. https://doi.org/10.1016/j.jnucmat.2013.01.306 -
S.-W. Kim, D.H. Heo, S.K. Lee, M.K. Jeon, W. Park, J.-M. Hur, S.-S. Hong, S.-C. Oh, E.-Y. Choi, A preliminary study of pilot-scale electrolytic reduction of
$UO_2$ using a graphite anode, Nucl. Eng. Technol. 49 (2017) 1451-1456. https://doi.org/10.1016/j.net.2017.05.004 - M.G. Adamson, D. Calef, R.W. Moir, Lithium nitrate as a fusion reactor coolant fluid?: a thermochemical assessment, J. Fusion Energy 5 (1986) 247-252. https://doi.org/10.1007/BF01050618
- C.M. Kramer, Z.A. Munir, J.V. Volponi, Simultaneous dynamic thermogrevimetry and mass spectrometry of the evaporation of alkali metal nitrates and nitrides, J. Therm. Anal. 27 (1983) 401-408. https://doi.org/10.1007/BF01914677
- C.H. Lee, T.-J. Kim, S. Park, S.-J. Lee, S.-W. Paek, D.-H. Ahn, S.-K. Cho, Effect of cathode material on the electrorefining of U in LiCl-KCl molten salts, J. Nucl. Mater. 488 (2017) 210-214. https://doi.org/10.1016/j.jnucmat.2017.03.023
- Y.H. Kang, J.H. Lee, S.C. Hwang, J.B. Shim, E.H. Kim, S.W. Park, Electrodeposition characteristics of uranium by using a graphite cathode, Carbon 44 (2006) 3113-3148. https://doi.org/10.1016/j.carbon.2006.08.007
- T. Koyama, M. Iizuka, Y. Shoji, R. Fujita, H. Tanaka, T. Kobyashi, M. Tokiwai, An experimental study of molten salt electrorefining of uranium using solid iron cathode and liquid cadmium cathode for development of pyrometallurgical reprocessing, J. Nucl. Sci. Technol. 34 (1997) 384-393. https://doi.org/10.1080/18811248.1997.9733678
피인용 문헌
- Employing high-temperature gas flux in a residual salt separation technique for pyroprocessing vol.51, pp.7, 2019, https://doi.org/10.1016/j.net.2019.05.023
- A Brief Guide to the Structure of High-Temperature Molten Salts and Key Aspects Making Them Different from Their Low-Temperature Relatives, the Ionic Liquids vol.125, pp.24, 2018, https://doi.org/10.1021/acs.jpcb.1c01065