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Journal of Nuclear Science and Technology Volume 55, 2018 - Issue 9
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Article

Analysis and optimization of the manifolds of the HCCB blanket for CFETR

Shuling XuInstitute of Plasma Physics, Chinese Academy of Sciences, Hefei, Anhui, ChinaView further author information
,
Mingzhun LeiInstitute of Plasma Physics, Chinese Academy of Sciences, Hefei, Anhui, ChinaCorrespondence[email protected]
View further author information
,
Yuntao SongInstitute of Plasma Physics, Chinese Academy of Sciences, Hefei, Anhui, ChinaView further author information
,
Sumei LiuInstitute of Plasma Physics, Chinese Academy of Sciences, Hefei, Anhui, ChinaView further author information
,
Kun LuInstitute of Plasma Physics, Chinese Academy of Sciences, Hefei, Anhui, ChinaView further author information
,
Kun PeiInstitute of Plasma Physics, Chinese Academy of Sciences, Hefei, Anhui, ChinaView further author information
&
Kun XuInstitute of Plasma Physics, Chinese Academy of Sciences, Hefei, Anhui, ChinaView further author information
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Pages 979-984 | Received 06 Sep 2017, Accepted 02 Apr 2018, Published online: 25 Apr 2018

References

  • Song YT, Wu WY, Du SJ, et al. Tokamak engineering mechanics. Berlin Heidelberg: Springer-Verlag; 2014. p. 99–156.
  • Wan YX, Li JG, Liu Y, et al. Overview of the present progress and activities on the CFETR. Nucl Fusion. 2017;57:102009.
  • Song YT, Wu ST, Li JG, et al. Concept design of CFETR tokamak machine. IEEE Trans Plasma Sci. 2014;42(3): 503–509.
  • Lei MZ, Song YT, Ye MY. Thermal hydraulic analysis of the HECLIC blanket breeder unit for CFETR. Int J Energy Res. 2015;39(3): 370–376.
  • Xu K, Ye MY, Song YT, et al. Neutronic analysis for CFETR with modular helium cooled lithium ceramic blanket. Proceedings of the 2017 25th International Conference on Nuclear Engineering (ICONE25); 2017 May 14-18; Shanghai, China: American Society of Mechanical Engineers; 2017. p. V005T05A035-V005T05A035.
  • Lei MZ, Song YT, Ye MY, et al. Conceptual design of a helium-cooled ceramic breeder blanket for CFETR. Fusion Sci Technol. 2015;68(4):772–779.
  • Lei MZ, Xu SL, Guo C, et al. Design and thermal-hydraulic evaluation of helium-cooled ceramic breeder blanket for China fusion engineering test reactor. Int J Energy Res. 2017;42(4): 1657–1663.
  • Ahn MY, Ku DY, Cho S, et al. Thermo-hydraulic analysis on Korean helium cooled solid breeder TBM with updated back manifolds design. Fusion Eng Des. 2011;86:2289–2292.
  • Hirai T, Pintsuk G. Thermo-mechanical calculations on operation temperature limits of tungsten as plasma facing material. Fusion Eng Des. 2007;82(4): 389–393.
  • Xu Z, Rey J, Fischer U, et al. Development of a DEMO helium cooled pebble bed (HCPB) breeder unit featured in flat plates with meandering channels. Germany: Forschungszentrum Karlsruhe; 2005. (Report no. 7181).

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