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Research Papers

New Exploration on TMSR: Redesign of the TMSR Lattice

[+] Author and Article Information
J. K. Zhao

Shanghai Nuclear Engineering Research &
Design Institute Co., Ltd.,
No. 29 Hongcao Road,
Shanghai 200233, China
e-mail: zhaojinkun@snerdi.com.cn

S. Y. Si

Shanghai Nuclear Engineering Research &
Design Institute Co., Ltd.,
No. 29 Hongcao Road,
Shanghai 200233, China
e-mail: hankspapa@snerdi.com.cn

Q. C. Chen

Shanghai Nuclear Engineering Research &
Design Institute Co., Ltd.,
No. 29 Hongcao Road,
Shanghai 200233, China
e-mail: chenqichang@snerdi.com.cn

H. Bei

Shanghai Nuclear Engineering Research &
Design Institute Co., Ltd.,
No. 29 Hongcao Road,
Shanghai 200233, China
e-mail: beihua@snerdi.com.cn

1Corresponding author.

Manuscript received October 25, 2017; final manuscript received August 13, 2018; published online January 24, 2019. Assoc. Editor: Jay F. Kunze.

ASME J of Nuclear Rad Sci 5(1), 011008 (Jan 24, 2019) (5 pages) Paper No: NERS-17-1187; doi: 10.1115/1.4041192 History: Received October 25, 2017; Revised August 13, 2018

Molten salt reactor (MSR) has been recognized as one of the next-generation nuclear power systems. Most MSR concepts are the variants evolved from the Oak Ridge National Laboratory (ORNL's) molten-salt breeder reactor (MSBR), which employs molten-salt as both fuel and coolant, and normally graphite is used as moderator. Many evaluations have revealed that such concepts have low breeding ratio and might present positive power coefficient. Facing these impediments, thorium molten salt reactor (TMSR) with redesigned lattice is proposed in this paper. Based on comprehensive investigation and screening, important lattice parameters including molten salt fuel composition, solid moderator material, lattice size, structure and lattice pitch to channel diameter (P/D) ratio are redesigned. In this paper, a fuel composition without BeF2 is adopted to increase the solubility for actinides (ThF4, UF4), and BeO is introduced as moderator to improve neutron economy. Moreover, lattice size and structure with cladding to separate fuel and moderator were also optimized. With these lattice parameters, TMSR has a high breeding ratio close to 1.14 and a short doubling time about 15 years. Meanwhile, a negative power coefficient is maintained. Based on this lattice design, TMSR can have excellent performance of safety and sustainability. SONG/TANG-MSR codes system is applied in the simulation, which is independently developed by Shanghai Nuclear Engineering Research & Design Institute (SNERDI).

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References

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Figures

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Fig. 1

Intersection of kinf and conversion ratio or breeding ratio (CBR) for different moderators

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Fig. 2

LiF–BeF2–ThF4 phase diagram plotted at 566 °C

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Fig. 3

Intersection of kinf and CBR versus 233U content for graphite lattice

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Fig. 4

P/D of intersections versus 233U content for graphite lattice

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Fig. 6

Conversion ratio or breeding ratio versus lattice pitch

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Fig. 7

P/D ratio versus lattice pitch

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Fig. 8

αpower versus lattice pitch

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Fig. 9

Temperature difference between fuel and moderator versus lattice pitch

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Fig. 10

Layout of 1/6 core

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Fig. 11

Power distribution of 1/6 core

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Fig. 12

Temperature distribution of 1/6 core

Tables

Errata

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