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| Corrosion of Materials for Molten Salt Reactor |
XU Yaxin, ZENG Chaoliu( ) |
| State Key Laboratory for Corrosion and Protection, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China |
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Abstract A molten salt reactor (MSR) is a kind of nuclear fission reactors using a molten salt mixture as the primary coolant and fuel. As one of the generation IV reactors MSR has received an increasing attention. The corrosion of materials is one of the technical obstacles to the development of MSR, and thus has been investigated extensively. Up to now, great progresses have been achieved<br>in the study of the corrosion of materials in MSR environments. This paper presents a comprehensive review of the progress in research work on the corrosion of materials for MSR.
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Received: 19 July 2013
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| [1] |
Yang M J, Ren J S, Zhou Z W. Introduction of R&D on generation IV nuclear energy system[J]. Int. Elec. Power China, 2004, 8(5): 30-35
|
|
(杨孟嘉, 任俊生, 周志伟. 第4代核能系统研发介绍[J]. 国际电力, 2004, 8(5): 30-35)
|
| [2] |
Grimes W R. Fluid Fuel Reactors-Chapter 13 [M]. New Jersey: Addison-Wesley, 1958
|
| [3] |
Williams D, Toth L, Clarno K. Assessment of candidate molten salt coolants for the advanced high temperature reactor (AHTR) [R]. Department of Energy, United States, 2006
|
| [4] |
Sabharwall P, Ebner M, Sohal M, et al. Molten salts for high temperature reactors: university of wisconsin molten salt corrosion and flow loop experiments-Issues identified and path forward [R]. Idaho National Laboratory, INL/EXT-10-18090, 2010
|
| [5] |
Olson L C, Ambrosek J W, Sridharan K, et al. Materials corrosion in molten LiF-NaF-KF salt[J]. J. Fluorine Chem., 2009, 130(1): 67-73
|
| [6] |
Misra A K, Daniel W J. Fluoride salts and container materials for thermal energy storage applications in the temperature range 973 to 1400K [R]. NASA Technical Memorandum89913 AIAA-87-9226, 1987
|
| [7] |
Delpech S, Cabet C, Slim C, et al. Molten fluorides for nuclear applications[J]. Mater. Today, 2010, 13(12): 34-41
|
| [8] |
Delpech S, Merle-Lucotte E, Auger T, et al. MSFR: Material issues and the effect of chemistry control [A]. GIF Symposium [C]. Paris, 2009
|
| [9] |
Williams D, Toth L, Clarno K. Assessment of candidate molten salt coolants for the advanced high temperature reactor (AHTR) [R]. Department of Energy, United States, 2006
|
| [10] |
Ignat'ev V V, Surenkov A I, Gnidoi I P, et al. Investigation of the corrosion resistance of nickel-based alloys in fluoride melts[J]. At. Energ., 2006, 101(4): 730-738
|
| [11] |
Koger J W, Litman A P. Mass transfer between Hastelloy N and Haynes alloy no. 25 in a molten sodium fluoroborate mixture [R]. Oak Ridge National Laboratory, ORNL-TM-3488, 1971
|
| [12] |
Fabre S, Cabet C, Cassayre L, et al. Electrochemical study of the corrosion of metals in moltenfluorides[J]. Mater. Sci. Forum, 2008595-598: 483-490
|
| [13] |
Olson L C. Materials corrosion in molten LiF-NaF-KF eutectic salt [D]. University of Wisconsin-Madison, 2009
|
| [14] |
Koger J W. Effect of FeF2 addition on mass transfer in a Hastelloy N-LiF-BeF2-UF4 thermal converction loop system [R]. Oak Ridge National Laboratory, ORNL-TM-4188, 1972
|
| [15] |
Sohal M S, Ebner M A, Sabarwal l P, et al. Engineering database of liquid salt thermophysical and thermochemical properties [R]. Idaho National Laboratory, 2010
|
| [16] |
Olson L, Sridharan K, Anderson M, et al. Intergranular corrosion of high temperature alloys in molten fluoride salts[J]. Mater. High Temp., 2010, 27(2): 145-149
|
| [17] |
Kondo M, Nagasaka T, Tsisar V, et al. Corrosion of reduced activation ferritic martensitic steel JLF-1 in purified Flinak at static and flowing conditions[J]. Fusion Eng. Des., 2010, 85(7-9): 1430-1436
|
| [18] |
Santarini G. Fused-salts-problems of corrosion and electrochemistry in the nuclear domain[J]. J. Nucl. Mater., 1981, 99: 269-283
|
| [19] |
You B J. Study on corrosion behavior of Nickel-based alloys in FLiNaK molten salt [D]. Hsinchu: National TsingHua Univisersity, 2010
|
|
(游柏坚. 镍基高温合金于FLINAK熔盐之腐蚀行为研究 [D]. 新竹: 国立清华大学, 2010)
|
| [20] |
Kondo M, Nagasaka T, Xu Q, et al. Corrosion characteristics of reduced activation ferritic steel, JLF-1 (8.92Cr-2W) in molten salts Flibe and Flinak[J]. Fusion Eng. Des., 2009, 84(7-11): 1081-1085
|
| [21] |
Briggs R B. Molten salt reactor program semiannual progress report for period ending [R]. Oak Ridge National Laboratory, ORNL-3282, 1962
|
| [22] |
Manly W D, Coobs J H, Devan J H, et al. Metallurgical problems in molten fluoride system [A]. International Conference on the Peaceful Uses of Atomic Energy [C]. Geneva: Oak Ridge National Laboratory, 1958
|
| [23] |
Keiser J R. Compatibility studies of potential molten-salt breeder reactor materials in molten fluoride salts [R]. Oak Ridge National Laboratory, ORNL-TM-5783, 1977
|
| [24] |
McCoy H E Jr. Status of molten development for molten salt reactors [R]. Oak Ridge National Laboratory, ORNL-TM-5920, 1978
|
| [25] |
McCoy H E Jr. Influence of Ti, Zr, and Hf Additions on the resistance of modified Hastelloy-N to irradiation damage [R]. Oak Ridge National Laboratory, ORNL-TM-3064, 1971
|
| [26] |
Watanabe T, Kondo M, Nagasaka T, et al. Corrosion characteristic of AlN, Y2O3, Er2O3 and Al2O3 in flinak for molten salt blanket system[J]. J. Plas. Fusion Res., 2010, 9: 342-347
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