In order to improve the breeding ratio and core safety, new thorium molten salt reactor (TMSR) core is designed. The new designed TMSR core is composed of hexagon moderator elements, which contain SiC tube to form a central fuel channel and employs BeO as moderator. The composition of the fuel salt, adopted in this core, is also optimized. Based on this core design, steady state and transient safety characteristic of TMSR are preliminarily analyzed using coupled multi-physics code. Power/temperature distribution and reactivity coefficients are analyzed for the steady state core, which demonstrated that the core has flat temperature distribution and large negative power coefficients at all power level. Transient simulations are carried out for power start-up, pump speed variation, loss of heat sink and so forth, the temperature and power response are also analyzed. The results indicate that the TMSR core power and temperature are closely related to the control rod position, velocity of flow and composition of fuel salt, and the new designed TMSR has excellent performance of safety under various operating conditions.
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2017 25th International Conference on Nuclear Engineering
July 2–6, 2017
Shanghai, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5783-0
PROCEEDINGS PAPER
New Design of Thorium Molten Salt Reactor Core and Preliminary Safety Analysis Available to Purchase
Chen Qi-chang,
Chen Qi-chang
Shanghai Nuclear Engineering Research & Design Institute, Shanghai, China
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Si Sheng-yi,
Si Sheng-yi
Shanghai Nuclear Engineering Research & Design Institute, Shanghai, China
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Zhao Jin-kun,
Zhao Jin-kun
Shanghai Nuclear Engineering Research & Design Institute, Shanghai, China
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Bei Hua
Bei Hua
Shanghai Nuclear Engineering Research & Design Institute, Shanghai, China
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Chen Qi-chang
Shanghai Nuclear Engineering Research & Design Institute, Shanghai, China
Si Sheng-yi
Shanghai Nuclear Engineering Research & Design Institute, Shanghai, China
Zhao Jin-kun
Shanghai Nuclear Engineering Research & Design Institute, Shanghai, China
Bei Hua
Shanghai Nuclear Engineering Research & Design Institute, Shanghai, China
Paper No:
ICONE25-66533, V005T05A018; 7 pages
Published Online:
October 17, 2017
Citation
Qi-chang, C, Sheng-yi, S, Jin-kun, Z, & Hua, B. "New Design of Thorium Molten Salt Reactor Core and Preliminary Safety Analysis." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues. Shanghai, China. July 2–6, 2017. V005T05A018. ASME. https://doi.org/10.1115/ICONE25-66533
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