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LLNL, Ampera partner to develop thorium-based TRISO fuel
Lawrence Livermore National Laboratory has formed a strategic partnership with Ampera to develop the company’s nuclear fuel concept through a project named THUNDER, for Thorium Unimodal Droplet Ejection for Reactors.
The focus of THUNDER is fabricating TRISO made with kernels of thorium rather than the usual uranium. LLNL and Ampera will evaluate and optimize liquid metal–jetting technology to produce highly uniform, spherical kernels of thorium-232 for later processing into TRISO fuel.
Wang Kee In
Nuclear Technology | Volume 134 | Number 2 | May 2001 | Pages 187-195
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT01-1
Articles are hosted by Taylor and Francis Online.
A numerical study was conducted to investigate the nuclear fuel assembly coolant flow mixing that is promoted by the flow deflectors on the grid spacer. Four typical flow deflectors (split vane, side-supported vane, swirl vane, and twisted vane) were chosen for this study. A single subchannel of one grid span is modeled using the flow symmetry. The predicted axial and lateral mean flow velocities, and the turbulent kinetic energy in the subchannel for the split-vane design, are in good agreement with the experimental results.The split vane and the twisted vane generate a large cross flow between the subchannels and a skewed elliptic swirling flow in the subchannel near the grid spacer. The cross flow rapidly decreases and the swirling flow becomes dominant downstream of the spacer. The side-supported vane induces a horizontally elongated elliptic swirl in the subchannel and a secondary flow in the near downstream of the spacer. The swirl vane produces a circular swirling flow in the subchannel and a negligible cross flow. For the twisted-vane and side-supported vane designs, the change in direction of the cross flow was predicted. The average turbulent kinetic energy in the subchannel sharply increases near the spacer and rapidly decreases to a fully developed level. In summary, the numerical results showed a somewhat large difference from the experimental results near the spacer but represented the overall characteristics of coolant mixing well in a nuclear fuel bundle with the flow deflectors on the grid spacer.