possesses good economy and inherent safety properties.By using the fuel assembly in molten-salt-cooled reactor
it is expected that the fuel load and release can be easier and reliable
which is similar to that widely used in LWR(Light Water Reactor).
Purpose
2
Based on spherical TRISO(Tristructural Isotropic)coated particle fuel elements
this study aims to design a fuel assembly model for the high-temperature molten-salt-cooled reactor.
Methods
2
The MCNP(A Monte Carlo N-Particle Transport Code)is employed to investigate the feasibility and behavior of the fuel assembly by analyzing the infinite multiplication factor
K
inf
the reactivity temperature coefficient(RTC)and the void reactivity(VR)of the FLiBe coolant as a function of the composition
density and wall thickness of the assembly material
the TRISO coated particles packing factor and the enrichment of
7
Li in FLiBe salt.
Results and Conclusion
2
The results show that carbon-based materials are significantly better than silicon-carbide-based materials for fuel assembly.Increasing the TRISO packing factor and enrichment of
7
Li helps to improve neutron economy and security properties of the reactor.
关键词
Keywords
references
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