Feasibility of an innovative long-life molten chloride-cooled reactor

Ming Lin; Mao-Song Cheng; Zhi-Min Dai

doi:10.1007/s41365-020-0751-7

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Feasibility of an innovative long-life molten chloride-cooled reactor

NUCLEAR ENERGY SCIENCE AND ENGINEERING | Updated：2021-01-26

- Feasibility of an innovative long-life molten chloride-cooled reactor
- Feasibility of an innovative long-life molten chloride-cooled reactor
- 核技术（英文版） 2020年31卷第4期文章编号：33
- Affiliations：
  
  1.(Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Jiading Campus, Shanghai 201800, China)
  2.(University of Chinese Academy of Sciences, Beijing 100049, China)
- Author bio：
  
  Corresponding author: Email address: mscheng@sinap.ac.cn.
- Funds：
  
  Strategic Pilot Science and Technology Project of Chinese Academy of Sciences
- DOI：10.1007/s41365-020-0751-7
  中图分类号：
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Ming Lin, Mao-Song Cheng, Zhi-Min Dai. Feasibility of an innovative long-life molten chloride-cooled reactor[J]. 核技术（英文版）, 2020,31(4):33

Ming Lin, Mao-Song Cheng, Zhi-Min Dai. Feasibility of an innovative long-life molten chloride-cooled reactor[J]. Nuclear Science and Techniques, 2020,31(4):33
Ming Lin, Mao-Song Cheng, Zhi-Min Dai. Feasibility of an innovative long-life molten chloride-cooled reactor[J]. 核技术（英文版）, 2020,31(4):33 DOI： 10.1007/s41365-020-0751-7.

Ming Lin, Mao-Song Cheng, Zhi-Min Dai. Feasibility of an innovative long-life molten chloride-cooled reactor[J]. Nuclear Science and Techniques, 2020,31(4):33 DOI： 10.1007/s41365-020-0751-7.

摘要

Abstract

Molten salt-cooled reactor is one of the six Gen-IV reactors with promising characteristics including safety, reliability, proliferation resistance, physical protection, economics, and sustainability. In this paper, a small innovative molten chloride-cooled fast reactor (MCCFR) with 30-year core and a target 120-MWt thermal power was presented. For its feasible study, neutronics, thermal-hydraulics, and radiation damage analysis were performed. The key design properties including kinetics parameters, reactivity swing, reactivity feedback coefficients, maximum accumulated displacement per atom (DPA) of reactor pressure vessel (RPV) and fuel cladding, and maximum coolant, cladding, and fuel temperatures were evaluated. The results showed the MCCFR could operate without refuelling for 30 years with overall negative reactivity feedback coefficients up the end of its life. During its 30-year life, the excess reactivity was well managed by constantly pulling out the control rods. The maximum accumulated DPA on RPV and fuel cladding were 8.92 dpa and 197.03 dpa, respectively, which are both below the design limits. Similarly, the maximum coolant, cladding and fuel center temperatures were all below the design limits during its entire lifetime. According to these results, the MCCFR core design with long life is feasible.

关键词

Keywords

Molten salt-cooled reactorNeutronicsRadiation damageThermal-hydraulics.

references

J. J. Bulmer, Fused Salt Fast Breeder: Reactor Design and Feasibility Study. United States Atomic Energy Commission, Technical Information Service Extension. 56, 8-204 (1957)

R. Petroski, H. Pavel, E.T. Neil, Thermal hydraulic design of a liquid salt-cooled flexible conversion ratio fast reactor. Nucl. Eng. Des. 239(12), 2612-2625 (2009). https://doi.org/10.1016/j.nucengdes.2009.07.012https://doi.org/10.1016/j.nucengdes.2009.07.012

Status of Small Reactor Designs Without On-Site Refuelling. Austria: Vienna. IAEA-TECDOC-1536 (2007)

M.W. Rosenthal, P.R. Kasten, R.B. Briggs, Molten-salt reactors-history, status, and potential. Nucl. Technol. 8, 107-117 (1970)

L. He, C.G. Yu, W. Guo et al., The temperature distribution of molten salt reactor under the outer salt layer blocked situation. Nucl. Tech. 41(5), 050601 (2018). https://doi.org/10.11889/j.0253-3219.2018.hjs.41.050601https://doi.org/10.11889/j.0253-3219.2018.hjs.41.050601 (in Chinese)

Q.Y. Li, B. Xu, C. Zhou et al., The optimization of flow rate distribution design of 373 MW molten salt reactor-liquid fuel. Nucl. Tech. 42(7), 070605 (2019). https://doi.org/10.11889/j.0253-3219.2019.hjs.42.070605https://doi.org/10.11889/j.0253-3219.2019.hjs.42.070605 (in Chinese)

C.W. Forsberg, The advanced high-temperature reactor: high-temperature fuel, liquid salt coolant, liquid-metal-reactor plant. Prog. Nucl. Energy 47, 32-43 (2005)

S.R. Greene, J.C. Gehin, D.E. Holcomb et al., Pre-Conceptual Design of a Fluoride-Salt-Cooled Small Modular Advanced High Temperature Reactor (SmAHTR). Technical Report TM-2010/199, (Oak Ridge National Laboratory, Tennessee, 2011). https://doi.org/10.2172/1008830https://doi.org/10.2172/1008830

R. Yan, S.H. Yu, Y. Zou et al., Study on neutronics design of ordered-pebble-bed fluoride-salt-cooled high-temperature experimental reactor. Nucl. Sci. Tech. 29, 81 (2018). https://doi.org/10.1007/s41365-018-0414-0https://doi.org/10.1007/s41365-018-0414-0

E. Shwageraus, H. Pavel, J. D. Michael, Liquid salt cooled flexible conversion ratio fast reactor: Neutronic design. Nucl. Eng. Des. 239(12), 2626-2645 (2009). https://doi.org/10.1016/j.nucengdes.2009.07.011https://doi.org/10.1016/j.nucengdes.2009.07.011

S.C. Zhou, L.Z Cao, H.C. Wu et al., SPARK-LS: A novel design of a compact liquid chloride salt cooled fast reactor based on tube-in-duct fuel concept. Ann. Nucl. Energy 128, 248-255 (2019). https://doi.org/10.1016/j.anucene.2019.01.020https://doi.org/10.1016/j.anucene.2019.01.020

J. A. Mascitti, M. Madariaga, Method for the Calculation of DPA in the Reactor Pressure Vessel of Atucha II. Sci. Technol. Nucl. Ins. 2011(12), 951-958 (2011). https://doi.org/10.1155/2011/534689https://doi.org/10.1155/2011/534689

P. Mohanakrishnan, Physics Design of Core, IGCAR Design Report, PFBR/01113/DN/1049 (Rev.C), Indira Gandhi Centre for Atomic Research, Kalpakkam (2004)

T.A. Mehlhorn, B.B. Cipiti, C.L. Olson et al., Fusion-fission hybrids for nuclear waste transmutation: A synergistic step between Gen-IV fission and fusion reactors. Fusion Eng. Des., 83(7-9), 948-953 (2008). https://doi.org/10.1016/j.fusengdes.2008.05.003https://doi.org/10.1016/j.fusengdes.2008.05.003

H.M. Şahin, Monte Carlo calculation of radiation damage in first wall of an experimental hybrid reactor. Ann. Nucl. Energy 34(11), 861-870 (2007). https://doi.org/10.1016/j.anucene.2007.04.011https://doi.org/10.1016/j.anucene.2007.04.011

T. K. Kim, C. Grandy, R.N. Hill, Carbide and nitride fuels for advanced burner reactor. No. IAEA-CN--176 (POWERPOINT PRESENTATIONS), 2009

C.R.F. Azevedo, Selection of fuel cladding material for nuclear fission reactors. Eng. Failure. Anal. 18(8), 1943-1962 (2011). https://doi.org/10.1016/j.engfailanal.2011.06.010https://doi.org/10.1016/j.engfailanal.2011.06.010

M. Lin, M.S. Cheng, Z.M. Dai, Development and preliminary validation of a sub-channel analysis code for molten chloride-cooled fast reactor. Nucl. Tech. 42, 010604 (2019). https://doi.org/10.11889/j.0253-3219.2019.hjs.42.010604https://doi.org/10.11889/j.0253-3219.2019.hjs.42.010604 (in Chinese)

J.K. Zhang, R.J. McClure, P.R. Trapp et al., Lead-bismuth eutectic technology for Hyperion reactor. J. Nucl. Mat. 441(1), 644-649 (2013). https://doi.org/10.1016/j.jnucmat.2013.04.079https://doi.org/10.1016/j.jnucmat.2013.04.079

Y. Zhang, J. Wallenius, A. Fokau, Transmutation of americium in a medium size sodium cooled fast reactor design. Ann. Nucl. Energy 37, 629-638 (2010). https://doi.org/10.1016/j.anucene.2009.12.014https://doi.org/10.1016/j.anucene.2009.12.014

R.C. Petroski, Design of a 2400MW liquid-salt cooled flexible conversion ratio reactor (Massachusetts Institute of Technology, 2008)

J. Sun, Q. Guo, Q.W. Zheng et al., Radiation response characteristics of an embeddable SOI radiation sensor. Nuclear Techniques. Nucl. Tech. 42(12), 120501 (2019).https://doi.org/10.11889/j.0253-3219.2019.hjs.42.120501https://doi.org/10.11889/j.0253-3219.2019.hjs.42.120501 (in Chinese)

D.F. Hollenbach, L.M. Petrie, N.F. Landers. KENO-VI: a general quadratic version of the KENO program. ORNL/TM-2005/39, Version 6

M.A. Jessee, M.D. DeHart, Triton: a multipurpose transport, depletion, and sensitivity and uncertainty analysis module. Oak Ridge National Laboratory, ORNL/TM-2005/39 Version 6 (2011)

B. Deng, J.G. Chen, L. He et al., Development and verification of a coupled code of steady-state neutronics and thermal-hydraulics for molten salt fast reactor. Nucl. Tech. 42(11), 110602 (2019). https://doi.org/10.11889/j.0253-3219.2019.hjs.42.110602https://doi.org/10.11889/j.0253-3219.2019.hjs.42.110602 (in Chinese)

M.S. Cheng, M. Lin, X.D. Zuo et al., Development and validation of a three-dimensional hexagonal nodal time-spatial kinetics code based on exponential transform. Nucl. Tech. 41(6), 060604 (2018). https://doi.org/10.11889/j.0253-3219.2018.hjs.41.060604https://doi.org/10.11889/j.0253-3219.2018.hjs.41.060604 (in Chinese)

http://www-nds.iaea.org/irdf2002/data/irdf2002damage.dathttp://www-nds.iaea.org/irdf2002/data/irdf2002damage.dat.

J. Chang, J. Cho, C. Gil et al., A simple method to calculate the displacement damage cross section of silicon carbide. Nucl. Eng. Technol. 46(4), 475-480 (2014). https://doi.org/10.5516/NET.01.2013.051https://doi.org/10.5516/NET.01.2013.051

B. Feng, K. Aydın, S. K. Mujid, Steady-state fuel behavior modeling of nitride fuels in FRAPCON-EP. J. Nucl. Mater. 427(1-3), 30-38(2012). https://doi.org/10.1016/j.jnucmat.2012.04.011https://doi.org/10.1016/j.jnucmat.2012.04.011

A. E. Waltar, R.T. Donald, V. T. Pavel, Fast spectrum reactors. Springer Science & Business Media (2012)

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