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Volume 40 Issue 6
Dec.  2019
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Li Yinghong, Huang Hao, Zhou Rongsheng, Yang Xiaodong. Criticality Safety Calculation and Analysis of Fresh Fuel Element Transport Containers for High Temperature Gas-Cooled Reactor[J]. Nuclear Power Engineering, 2019, 40(6): 64-71. doi: 10.13832/j.jnpe.2019.06.0064
Citation: Li Yinghong, Huang Hao, Zhou Rongsheng, Yang Xiaodong. Criticality Safety Calculation and Analysis of Fresh Fuel Element Transport Containers for High Temperature Gas-Cooled Reactor[J]. Nuclear Power Engineering, 2019, 40(6): 64-71. doi: 10.13832/j.jnpe.2019.06.0064

Criticality Safety Calculation and Analysis of Fresh Fuel Element Transport Containers for High Temperature Gas-Cooled Reactor

doi: 10.13832/j.jnpe.2019.06.0064
  • Publish Date: 2019-12-15
  • In this paper, the HTR-10 fuel pebbles were described by MCNP5 program which is based on the Monte Carlo method. Eight different fuel pebble models were constructed, and their keff values and computation time have been compared to obtain an optimal fuel pebble model. Then, using this optimal fuel pebble model, a HTGR fresh fuel elements transport container model was described by MCNP5. And a series of criticality influencing factors are calculated and analyzed, such as thickness of the neutron absorbing plate, wall thickness of the aluminum alloy tube, thickness of the outer container, buffer layer materials, reflector materials, deformation, structural loss, water submergence and infinite container arrays. The results showed that the HTGR fresh fuel elements transport container always remains in the criticality safety state, no matter under normal transportation conditions or under accidental transportation conditions. And its criticality safety index (CSI) can be set to zero.

     

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