2019, Volume 21, Issue 1
Strategic Study of CAE >> 2019, Volume 21, Issue 1 doi: 10.15302/J-SSCAE-2019.01.005
Development Strategy for Thorium Molten Salt Reactor Materials
Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China
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Abstract
As one of the six General IV nuclear reactors, the molten salt reactor (MSR) has received an increasing attention around the world owing to its high energy conversion efficiency, inherent safety feature, and application of the thorium fuel. However, major components for MSRs are facing great challenges due to the extreme environments of high temperature, corrosive molten fluoride salt, and neutron irradiation inside the MSRs. In this paper, requirements for the MSR materials are analyzed; the development history, current status, and existing problems of the key MSR materials (including alloy structure materials and nuclear graphite) are depicted; key technical problems to be solved during the current construction of experimental MSRs are pointed out; and the development strategy for the MSR materials is proposed, based on the research and development plan for the MSRs.
Keywords
molten salt reactor ; high temperature materials ; material-molten salt compatibility ; irradiation effect
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References
[ 1 ] Rosenthal M W, Haubenreich P N, Briggs R B. The development status of molten-salt breeder reactors [R]. Tennessee: Oak Ridge National Laboratory, 1972. link1
[ 2 ] Jiang L, Xu Z F, Li Z J. The effect of silicon additions on the thermal stability and morphology of carbides in a Ni-Mo-Cr superalloy [R]. Hawaii: 8 Pacific Rim International Congress on Advanced Materials and Processing, 2013. link1
[ 3 ] Xu Z F, Jiang L, Dong J S. The effect of silicon on precipitation and decomposition behaviors of M6C carbide in a Ni-Mo-Cr superalloy [J]. Journal of Alloys & Compounds, 2015 (620): 197–203. link1
[ 4 ] Xu Z F, Dong J S, Jiang L. Effects of Si addition and longterm thermal exposure on the tensile properties of a Ni-Mo-Cr superalloy [J]. Acta Metallurgica Sinica (English Letters), 2015 (8): 951–957. link1
[ 5 ] Jiang L, Zhang W Z, Xu Z F. M2C and M6C carbide precipitation in Ni-Mo-Cr based superalloys containing silicon [J]. Materials & Design, 2016 (112): 300–308. link1
[ 6 ] McCoy H E. Status of materials development for molten salt reactor [R]. Tennessee: Oak Ridge National Laboratory, 1978. link1
[ 7 ] Cheng H W, Han F F, Jia Y Y, et al. Effects of Te on intergranular embrittlement of a Ni-16Mo-7Cr alloy [J]. Journal of Nuclear Materials, 2015 (461): 122–128. link1
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