Molten salt reactors (MSRs) have seen a marked resurgence of interest over the past few decades, highlighted by their inclusion as one of the six Generation IV reactor types. The MSRs are characterized by using the fluid-fuel, so that their technologies are fundamentally different from those used in the conventional solid-fuel reactors. In this paper, the attention is focused on the behaviors of a MSR in the presence of localized perturbations caused by fissile precipitates. A neutron kinetic model considering the fuel salt flow is established based on the neutron diffusion theory, which consists of two-group neutron diffusion equations for the fast and thermal neutron fluxes and six-group balance equations for delayed neutron precursors, and the group constants dependent on the temperature are calculated by the code DRAGON. In addition, the k-epsilon turbulent model is adopted to establish the flow and heat transfer. The thermo-hydraulic and neutronic models which are coupled through the temperature, heat source and velocity are coded in a program. The effects of the localized perturbation on the distributions of power, temperature, neutron fluxes and delayed neutron precursors are obtained and discussed in detail. The results provide some valuable information for the research and design of this new generation reactor.
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2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference
July 30–August 3, 2012
Anaheim, California, USA
Conference Sponsors:
- Nuclear Engineering Division
- Power Division
ISBN:
978-0-7918-4496-0
PROCEEDINGS PAPER
Numerical Analysis for a Molten Salt Reactor in the Presence of Fissile Lump
Yao Xiao,
Yao Xiao
Xi’an Jiaotong University, Xi’an, Shaanxi, China
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Dalin Zhang,
Dalin Zhang
Xi’an Jiaotong University, Xi’an, Shaanxi, China
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Zhangpeng Guo,
Zhangpeng Guo
Xi’an Jiaotong University, Xi’an, Shaanxi, China
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Suizheng Qiu
Suizheng Qiu
Xi’an Jiaotong University, Xi’an, Shaanxi, China
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Yao Xiao
Xi’an Jiaotong University, Xi’an, Shaanxi, China
Dalin Zhang
Xi’an Jiaotong University, Xi’an, Shaanxi, China
Zhangpeng Guo
Xi’an Jiaotong University, Xi’an, Shaanxi, China
Suizheng Qiu
Xi’an Jiaotong University, Xi’an, Shaanxi, China
Paper No:
ICONE20-POWER2012-54384, pp. 591-598; 8 pages
Published Online:
October 30, 2013
Citation
Xiao, Y, Zhang, D, Guo, Z, & Qiu, S. "Numerical Analysis for a Molten Salt Reactor in the Presence of Fissile Lump." Proceedings of the 2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference. Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems. Anaheim, California, USA. July 30–August 3, 2012. pp. 591-598. ASME. https://doi.org/10.1115/ICONE20-POWER2012-54384
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