TY - JOUR
T1 - Numerical analysis for a molten salt reactor in the presence of localized perturbations
AU - Xiao, Yao
AU - Zhang, Dalin
AU - Guo, Zhangpeng
AU - Wu, Yingwei
AU - Tian, Wenxi
AU - Su, Guanghui
AU - Qiu, Suizheng
PY - 2012/9
Y1 - 2012/9
N2 - 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 an MSR in the presence of localized perturbations caused by fissile precipitates and gas bubbles. 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 are coupled through the temperature, heat source and velocity. 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.
AB - 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 an MSR in the presence of localized perturbations caused by fissile precipitates and gas bubbles. 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 are coupled through the temperature, heat source and velocity. 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.
KW - Fissile precipitate
KW - Gas bubble
KW - Localized perturbation
KW - Molten salt reactor
KW - Neutron diffusion
UR - https://www.scopus.com/pages/publications/84862698288
U2 - 10.1016/j.pnucene.2012.05.005
DO - 10.1016/j.pnucene.2012.05.005
M3 - 文章
AN - SCOPUS:84862698288
SN - 0149-1970
VL - 60
SP - 61
EP - 72
JO - Progress in Nuclear Energy
JF - Progress in Nuclear Energy
ER -