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http://dx.doi.org/10.1016/j.net.2019.03.006

Excluding molten fluoride salt from nuclear graphite by SiC/glassy carbon composite coating  

He, Zhao (Key Laboratory of Carbon Materials, Institute of Coal Chemistry, Chinese Academy of Sciences)
Song, Jinliang (Key Laboratory of Nuclear Radiation and Nuclear Energy Technology, Shanghai Institute of Applied Physics, Chinese Academy of Sciences)
Lian, Pengfei (Key Laboratory of Carbon Materials, Institute of Coal Chemistry, Chinese Academy of Sciences)
Zhang, Dongqing (Key Laboratory of Carbon Materials, Institute of Coal Chemistry, Chinese Academy of Sciences)
Liu, Zhanjun (Key Laboratory of Carbon Materials, Institute of Coal Chemistry, Chinese Academy of Sciences)
Publication Information
Nuclear Engineering and Technology / v.51, no.5, 2019 , pp. 1390-1397 More about this Journal
Abstract
SiC coating and SiC/glassy carbon composite coating were prepared on IG-110 nuclear graphite (Toyo Tanso Co., Ltd., Japan) to strengthen its inertness to molten fluoride salt used in molten salt reactor (MSR). Two kinds of modified graphite were obtained and correspondingly named as IG-110-1 and IG-110-2, which referred to modified IG-110 with a single SiC coating and a SiC/glassy carbon composite coating, respectively. Both structure and property of modified graphite were carefully researched and contrasted with virgin IG-110. Results indicated that modified graphite presented better comprehensive properties such as more compact structure and higher resistance to molten salt infiltration. With the protection of coatings, the infiltration amounts of fluoride salt into modified graphite were much less than that into virgin IG-110 at the same circumstance. Especially, the infiltration amount of fluoride salt into IG-110-2 under 5 atm was merely 0.26 wt%, which was much less than that into virgin IG-110 under 1.5 atm (13.5 wt%) and the critical index proposed for nuclear graphite used in MSR (0.5 wt%). The SiC/glassy carbon composite coating gave rise to highest resistance to molten salt infiltration into IG-110-2, and thus demonstrated it could be a promising protective coating for nuclear graphite used in MSR.
Keywords
Composite coating; Nuclear graphite; Molten salt reactor; Molten salt infiltration;
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1 E. Capelli, O. Bene-s, R.J.M. Konings, Thermodynamic assessment of the $LiF-NaF-BeF_2-ThF_4-UF_4$ system, J. Nucl. Mater. 449 (1-3) (2014) 111-121.   DOI
2 X.H. An, J.H. Cheng, H.Q. Yin, et al., Thermal conductivity of high temperature fluoride molten salt determined by laser flash technique, Int. J. Heat Mass Transf. 90 (2015) 872-877.   DOI
3 R.B. Briggs, Molten-Salt Reactor Program Progress Report, Oak Ridge National Laboratory, USA, 1961. ORNL-3122.
4 M.W. Rosenthal, P.N. Haubenreich, R.B. Briggs, The Development Status of Molten-Salt Breeder Reactors, Oak Ridge National Laboratory, USA, 1972. ORNL-4812.
5 R.B. Briggs, Molten-salt Reactor Program Semi Annual Progress Report, Oak Ridge National Laboratory, USA, 1964. ORNL-3708.
6 H. Mccoy, R. Beatty, W. Cook, et al., New developments in materials for molten salt reactors, Nucl. Appl. Technol. 8 (2) (1970) 156-169.   DOI
7 X.J. He, J.L. Song, L. Xu, et al., Protection of nuclear graphite toward liquid fluoride salt by isotropic pyrolytic carbon coating, J. Nucl. Mater. 442 (1-3) (2013) 306-308.   DOI
8 X.J. He, J.L. Song, J. Tan, et al., SiC coating: an alternative for the protection of nuclear graphite from liquid fluoride salt, J. Nucl. Mater. 448 (1-3) (2014) 1-3.   DOI
9 R.B. Briggs, M.W. Rosenthal, P.N. Haubenreich, Molten Salt Reactor Program Semiannual Progress Report, Oak Ridge National Laboratory, USA, 1971. ORNL-4728.
10 R.B. Briggs, P.R. Kasten, Molten-salt Reactor Program Semiannual Progress Report, Oak Ridge National Laboratory, USA, 1963. ORNL-3419.
11 S. Dutta, Effects of various consolidation techniques on microstructure, strength, and reliability of alpha-SiC, Ceram. Trans. 2 (1989) 215-226. Silicon Carbide '287, printed in United States.
12 X. Yang, Q. Huang, Z. Su, et al., Resistance to oxidation and ablation of SiC coating on graphite prepared by chemical vapor reaction, Corros. Sci. 75 (2013) 16-27.   DOI
13 Y. Kim, C. Jang, E.-S. Kim, SiC coating on various nuclear-grade graphite substrates by chemical vapor reaction, J. Ceram. Process. Res. 15 (5) (2014) 294-297.   DOI
14 Pimenta MA, G. Dresselhaus, M.S. Dresselhaus, et al., Studying disorder in graphite-based systems by Raman spectroscopy, Phys. Chem. Chem. Phys. 9 (11) (2007) 1276-1291.   DOI
15 K.S. Xiao, Q.G. Guo, Z.J. Liu, et al., Influence of fiber coating thickness on microstructure and mechanical properties of carbon fiber-reinforced zirconium diboride based composites, Ceram. Int. 40 (1) (2014) 1539-1544.   DOI
16 ASTM C695-91, Standard Test Method for Compressive Strength of Carbon and Graphite, 2010.
17 F. Tuinstra, J.L. Koenig, Raman spectrum of graphite, J. Chem. Phys. 53 (3) (1970) 1126-1130.   DOI
18 L. Nikiel, P.W. Jagodzinski, Raman-spectroscopic characterization of graphitesa reevaluation of spectra/structure correlation, Carbon 31 (8) (1993) 1313-1317.   DOI
19 T. Jawhari, A. Roid, J. Casado, Raman spectroscopic characterization of some commercially available carbon black materials, Carbon 33 (11) (1995) 1561-1565.   DOI
20 S. Chakraborty, D. Debnath, A.R. Mallick, et al., Microscopic, mechanical and thermal properties of spark plasma sintered $ZrB_2$ based composite containing polycarbosilane derived SiC, Int. J. Refract. Metals Hard Mater. 52 (2015) 176-182.   DOI
21 B. Vriesema, Aspects of Molten Fluorides as Heat Transfer Agents for Power Generation, University of Technology the Netherlands, Department of Mechanical Engineering, 1979.
22 GB/T 21650.1-2008/ISO15901-1, Pore Size Distribution and Porosity of Solid Materials by Mercury Porosimetry and Gas Adsorption-Part 1: Mercury Porosimetry, 2005, p. 1.
23 Z.T. He, L.N. Gao, X. Wang, et al., Improvement of stacking order in graphite by molten fluoride salt infiltration, Carbon 72 (2014) 304-311.   DOI
24 M.C. Huang, HsishengTeng, Urea impregnation to enhance porosity development of carbons prepared from phenol-formaldehyde resins, Carbon 40 (6) (2002) 955-958.   DOI
25 Z. He, P.F. Lian, Y. Song, et al., Improving molten fluoride salt and $Xe^{135}$ barrier property of nuclear graphite by phenolic resin impregnation process, J. Nucl. Mater. 499 (2018) 79-87.   DOI
26 S.S. Tzeng, J.H. Pan, Densification of two-dimensional carbon/carbon composites by pitch impregnation, Mater. Sci. Eng. 316 (2001) 127-134.   DOI
27 J.L. Song, Y.L. Zhao, J.P. Zhang, et al., Preparation of binderless nanopore-isotropic graphite for inhibiting the liquid fluoride salt and $Xe^{135}$ penetration for molten salt nuclear reactor, Carbon 79 (2014) 36-45.   DOI
28 J.J. Biernacki, G.P. Wotzak, Stoichiometry of the $C+SiO_2$ reaction, J. Am. Ceram. Soc. 72 (1) (1989) 122-129.   DOI
29 P.F. Lian, J.L. Song, Z.J. Liu, et al., Preparation of ultrafine-grain graphite by liquid dispersion technique for inhibiting the liquid fluoride salt infiltration, Carbon 102 (2016) 208-215.   DOI
30 J.L. Song, Q.G. Guo, X.Q. Gao, et al., $Mo_2C$ intermediate layers for the wetting and infiltration of graphite foams by liquid copper, Carbon 49 (10) (2011) 3165-3170.   DOI
31 X.M. Yang, M. Liu, Y.T. Gao, et al., Effect of oxygen on the corrosion of SiC in LiF-NaF-KF molten salt, Corros. Sci. 103 (2016) 165-172.   DOI
32 W.T. Zhang, B.L. Zhang, J.L. Song, et al., Microstructure and molten salt impregnation characteristics of a micro-fine grain graphite for use in molten salt reactors, N. Carbon Mater. 31 (6) (2016) 585-593.   DOI
33 T. Abram, S. Ion, Generation-IV nuclear power: a review of the state of the science, Energy Policy 36 (12) (2008) 4323-4330.   DOI
34 M.S. Sohal, M.A. Ebner, P. Sabharwall, et al., Engineering Database of Liquid Salt Thermophysical and Thermochemical Properties, 2010. Technical Report INL/EXT-10-18297.
35 D.E. Holcomb, S.M. Cetiner, An Overview of Liquid-Fluoride-Salt Heat Transport Systems, Oak Ridge National Laboratory, USA, 2010. ORNL/TM-2010/156.
36 J.L. Song, Y.L. Zhao, X.J. He, et al., Preparation of pyrolytic carbon coating on graphite for inhibiting liquid fluoride salt and $Xe^{135}$ penetration for molten salt breeder reactor, J. Nucl. Mater. 456 (2015) 33-40.   DOI
37 Z. He, P.F. Lian, Y. Song, et al., Protecting nuclear graphite from liquid fluoride salt and oxidation by SiC coating derived from polycarbosilane, J. Eur. Ceram. Soc. 38 (2) (2018) 453-462.   DOI
38 V. Bernardet, S. Gomes, S. Delpeux, et al., Protection of nuclear graphite toward fluoride molten salt by glassy carbon deposit, J. Nucl. Mater. 384 (3) (2009) 292-302.   DOI
39 S. Ueta, J. Sumita, T. Shibata, et al., R&D plan for development of oxidation-resistant graphite and investigation of oxidation behavior of SiC coated fuel particle to enhance safety of HTGR, Nucl. Eng. Des. 271 (2014) 309-313.   DOI
40 Y.F. Gu, J.X. Liu, Y. Wang, et al., Corrosion behavior of TiC-SiC composite ceramics in molten FLiNaK salt, J. Eur. Ceram. Soc. 37 (7) (2017) 2575-2582.   DOI
41 Y.H. Yun, Y.H. Park, M.Y. Ahn, et al., CVR-SiC coating of graphite pebbles for fusion blanket application, Ceram. Int. 40 (1) (2014) 879-885.   DOI
42 Y. Lee, Y.H. Yun, Y.H. Park, et al., Surface coating of graphite pebbles for Korean HCCR TBM, Fusion Eng. Des. 89 (7-8) (2014) 1734-1738.   DOI
43 T. Iseki, M. Ishida, H. Suzuki, Thermal shock behavior of SiC coatings for fusion reactor applications, J. Nucl. Sci. Technol. 19 (7) (1982) 587-592.   DOI