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).
Skip Nav Destination
Article navigation
January 2019
Research-Article
New Exploration on TMSR: Redesign of the TMSR Lattice
J. K. Zhao,
J. K. Zhao
Shanghai Nuclear Engineering Research &
Design Institute Co., Ltd.,
No. 29 Hongcao Road,
Shanghai 200233, China
e-mail: zhaojinkun@snerdi.com.cn
Design Institute Co., Ltd.,
No. 29 Hongcao Road,
Shanghai 200233, China
e-mail: zhaojinkun@snerdi.com.cn
Search for other works by this author on:
S. Y. Si,
S. Y. Si
Shanghai Nuclear Engineering Research &
Design Institute Co., Ltd.,
No. 29 Hongcao Road,
Shanghai 200233, China
e-mail: hankspapa@snerdi.com.cn
Design Institute Co., Ltd.,
No. 29 Hongcao Road,
Shanghai 200233, China
e-mail: hankspapa@snerdi.com.cn
Search for other works by this author on:
Q. C. Chen,
Q. C. Chen
Shanghai Nuclear Engineering Research &
Design Institute Co., Ltd.,
No. 29 Hongcao Road,
Shanghai 200233, China
e-mail: chenqichang@snerdi.com.cn
Design Institute Co., Ltd.,
No. 29 Hongcao Road,
Shanghai 200233, China
e-mail: chenqichang@snerdi.com.cn
Search for other works by this author on:
H. Bei
H. Bei
Shanghai Nuclear Engineering Research &
Design Institute Co., Ltd.,
No. 29 Hongcao Road,
Shanghai 200233, China
e-mail: beihua@snerdi.com.cn
Design Institute Co., Ltd.,
No. 29 Hongcao Road,
Shanghai 200233, China
e-mail: beihua@snerdi.com.cn
Search for other works by this author on:
J. K. Zhao
Shanghai Nuclear Engineering Research &
Design Institute Co., Ltd.,
No. 29 Hongcao Road,
Shanghai 200233, China
e-mail: zhaojinkun@snerdi.com.cn
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
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
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
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. Jan 2019, 5(1): 011008 (5 pages)
Published Online: January 24, 2019
Article history
Received:
October 25, 2017
Revised:
August 13, 2018
Citation
Zhao, J. K., Si, S. Y., Chen, Q. C., and Bei, H. (January 24, 2019). "New Exploration on TMSR: Redesign of the TMSR Lattice." ASME. ASME J of Nuclear Rad Sci. January 2019; 5(1): 011008. https://doi.org/10.1115/1.4041192
Download citation file:
93
Views
Get Email Alerts
Cited By
Development of Risk Informed Aging Management Program in Decommissioning
ASME J of Nuclear Rad Sci
Legal Issues of Fusion Technologies
ASME J of Nuclear Rad Sci
Electrochemical Activity Measurements of UCl3 in Molten NaCl-MgCl2-UCl3
ASME J of Nuclear Rad Sci (July 2024)
Related Articles
Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor
ASME J of Nuclear Rad Sci (January,2015)
Study on the Coupled Neutronic and Thermal-Hydraulic Characteristics of the New Concept Molten Salt Reactor
J. Eng. Gas Turbines Power (October,2010)
The Transfer of Xenon-135 to Molten Salt Reactor Graphite
ASME J of Nuclear Rad Sci (January,0001)
Verification and Geometry Optimization of a One Fluid Molten Salt Reactor (OFMSR) with Fixed Volume
ASME J of Nuclear Rad Sci (January,0001)
Related Proceedings Papers
Related Chapters
New Generation Reactors
Energy and Power Generation Handbook: Established and Emerging Technologies
Regional/Neutron Overpower Protection (ROP/NOP)
Fundamentals of CANDU Reactor Physics
Studies Performed
Closed-Cycle Gas Turbines: Operating Experience and Future Potential