Neutronics analysis for MSR cell with different fuel salt channel geometries


The neutronic properties of molten salt reactors (MSRs) differ from those of traditional solid fuel reactors owing to their nuclear fuel particularity. Based on the Monte-Carlo N particle transport code, the effects of the size and shape of the fuel salt channel on the neutron physics of an MSR cell are investigated systematically in this study. The results show that the infinite multiplication factor (k) first increases and then decreases with the change in the graphite cell size under certain fuel volume fraction (FVF) conditions. For the same FVF and average chord length, when the average chord length is relatively small, the k values for different fuel salt channel shapes agree well. When the average chord length is relatively large, the k values for different fuel salt channel shapes differ significantly. In addition, some examples of practical applications of this study are presented, including cell selection for the core and thermal expansion displacement analysis of the cell.

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  1. 1.

    R.C. Briant, A.M. Weinberg, Molten fluorides as power reactor fuel. Nucl. Sci. Eng. 2, 797–803 (1957).

    Article  Google Scholar 

  2. 2.

    E.S. Bettis, R.W. Schroeder, G.A. Cristy et al., The aircraft reactor experiment-design and construction. Nucl. Sci. Eng. 2, 804–825 (1957).

    Article  Google Scholar 

  3. 3.

    P.N. Haubenreich, J.R. Engel, Experience with the Molten-Salt Reactor experiment. Nucl. Appl. Technol. 8, 118–136 (1970).

    Article  Google Scholar 

  4. 4.

    S. Ling, Zero Power Experiment Device in Shanghai Institute of Nuclear Research. Chin. J. Nucl. Sci. Eng. 2, 23–24 (1984). (in Chinese)

    Google Scholar 

  5. 5.

    Y. Liu, R. Yan, Y. Zou et al., Criticality properties and control rod worth of the critical experiment device for MSR research. Nucl. Technol. 204, 203–212 (2018).

    Article  Google Scholar 

  6. 6.

    Y. Liu, R. Yan, Y. Zou et al., Neutron flux distribution and conversion ratio of Critical Experiment Device for molten salt reactor research. Ann. Nucl. Energy 133, 707–717 (2019).

    Article  Google Scholar 

  7. 7.

    USDOE, A Technology Roadmap for Generation IV Nuclear Energy Systems. J. Philosophical Rev, 66, 239-241(2002). GIF-002-00

  8. 8.

    I. L. Pioro, Handbook of Generation IV Nuclear Reactors. M. Elsevier Inc, (2014).

  9. 9.

    M. Brovchenko, D. Heuer, E. Lucotte et al., Design-related studies for the preliminary safety assessment of the Molten Salt Fast Reactor. Nucl. Sci. Eng. 175, 329–339 (2012).

    Article  Google Scholar 

  10. 10.

    M. Jiang, H. Xu, Z. Dai, The Future of advanced nuclear fission energy-TMSR nuclear energy systems. Bull. Chin. Acad. Sci. 27, 366–374 (2012). (in Chinese)

    Google Scholar 

  11. 11.

    X. Cai, Z. Dai, H. Xu, Thorium molten salt reactor nuclear energy system. Physics 45, 578–590 (2016). (in Chinese)

    Article  Google Scholar 

  12. 12.

    Q. Ye, X. Li, Z. Yu, et al., China electrical engineering canon sixth volume nuclear power generation engineering. Beijing: China Electric Power Press, 1142–1144 (2009). (in Chinese)

  13. 13.

    S. Yu, X. Cao, B. Lan, Analysis of moderator temperature coefficient with neutron spectrum for pressurized water reactors. Atomic Energy Sci. Technol. 47, 1594–1598 (2013). (in Chinese)

    Google Scholar 

  14. 14.

    J.S. Kim, Y.S. Jeon, S.D. Park et al., Analysis of high burnup pressurized water reactor fuel using uranium, plutonium, neodymium, and cesium isotope correlations with burnup. Nucl. Eng. Technol. 47, 924–933 (2015).

    Article  Google Scholar 

  15. 15.

    K. Zhuang, L. Cao, Y. Zheng et al., Studies on the molten salt reactor: code development and neutronics analysis of MSRE-type design. J. Nucl. Sci. Technol. 52, 251–263 (2015).

    Article  Google Scholar 

  16. 16.

    Y. Liu, L. Mei, X. Cai, Physics research for Molten Salt Reactor with different core boundaries. Nucl. Tech. 36, 030601 (2013). (in Chinese)

    Google Scholar 

  17. 17.

    A. Nuttin, D. Heue, A. Billebaud et al., Potential of thorium molten salt reactors: detailed calculations and concept evolution with a view to large scale energy production. Progress Nucl. Energy 46, 77–99 (2005).

    Article  Google Scholar 

  18. 18.

    Y. Liu, R. Guo, X. Cai et al., Breeding properties study on high-power thorium molten salt reactor. ASME J. Nucl. Rad. Sci. 5, 011003 (2019).

    Article  Google Scholar 

  19. 19.

    S. Yu, Y. Liu, P. Yang et al., Effect analysis of core structure changes on reactivity in molten salt experimental reactor. Nucl. Tech. 42, 020603 (2019). (in Chinese)

    Article  Google Scholar 

  20. 20.

    W. Joe, J. Durkee, M.R. James et al., The MCNP6 delayed-particle feature. Nucl. Technol. 180, 336–354 (2012).

    Article  Google Scholar 

  21. 21.

    G. Zhu, Y. Zou, M. Li et al., Development of burn up calculation code for pebble-bed high temperature reactor at equilibrium state. Atomic Energy Sci. Technol. 5, 890–896 (2015). (in Chinese)

    Article  Google Scholar 

  22. 22.

    Z. Xie, Physical analysis of nuclear reactors. Beijing: Atomic Energy Press, 139–160(2004). (in Chinese)

  23. 23.

    M.B. Chadwick, P. Obložinský, M. Herman et al., ENDF/B-VII.0: next generation evaluated nuclear data library for nuclear science and technology. Nucl. Data Sheets 107, 29313060 (2017).

    Article  Google Scholar 

  24. 24.

    J. Sun, Y. Zou, R. Yan et al., Study on the effect of core volume of PB-FHR on coolant temperature reactivity coefficient. Nucl. Tech. 37, 120603 (2014). (in Chinese)

    Article  Google Scholar 

  25. 25.

    J. Sun, Y. Zou, R. Yan et al., Analysis of the coolant reactivity coefficients of FHRs with Li-6 contents of coolant. Nucl. Tech. 37, 090605 (2014)

    Google Scholar 

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Author information




All authors contributed to the study conception and design. Material preparation, data collection, and analysis were performed by Shi-He Yu, Ya-Fen Liu, and Pu Yang. The first draft of the manuscript was written by Ya-Fen Liu, and all authors commented on previous versions of the manuscript. All authors read and approved the final manuscript.

Corresponding author

Correspondence to Ya-Fen Liu.

Additional information

This work was supported by the Chinese TMSR Strategic Pioneer Science and Technology Project (No.XDA02010000), the Frontier Science Key Program of Chinese Academy of Sciences (No.QYZDY-SSW-JSC016), and the Shanghai Sailing Program (No. Y931021031).

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Yu, SH., Liu, YF., Yang, P. et al. Neutronics analysis for MSR cell with different fuel salt channel geometries. NUCL SCI TECH 32, 9 (2021).

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  • Molten salt reactor
  • Fuel salt channel
  • Cell geometry
  • Neutronics