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Volume 44 Issue 2
Apr.  2023
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Cui Menglei, Guo Jiong, Wang Yizhen, Liu Baokun, Kong Boran, Zhu Kaijie, Li Fu. Pebble-Bed High-Temperature Gas-Cooled Reactor Burnup Uncertainty Analysis Based on Fine Burnup History and Fine Burnup Chains[J]. Nuclear Power Engineering, 2023, 44(2): 9-14. doi: 10.13832/j.jnpe.2023.02.0009
Citation: Cui Menglei, Guo Jiong, Wang Yizhen, Liu Baokun, Kong Boran, Zhu Kaijie, Li Fu. Pebble-Bed High-Temperature Gas-Cooled Reactor Burnup Uncertainty Analysis Based on Fine Burnup History and Fine Burnup Chains[J]. Nuclear Power Engineering, 2023, 44(2): 9-14. doi: 10.13832/j.jnpe.2023.02.0009

Pebble-Bed High-Temperature Gas-Cooled Reactor Burnup Uncertainty Analysis Based on Fine Burnup History and Fine Burnup Chains

doi: 10.13832/j.jnpe.2023.02.0009
  • Received Date: 2022-06-08
  • Rev Recd Date: 2022-11-04
  • Publish Date: 2023-04-15
  • The fuel element burnup history becomes extremely complex as a result of the multi-pass of the fuel pebble through the reactor core in fuel management of the pebble-bed high-temperature gas-cooled reactor (PB-HTGR). The core physical design program VSOP of PB-HTGR can provide a fine burnup history of fuel elements, but it involves only a small number of burn-up chains and nuclide species. The burnup calculation program NUIT developed independently by Tsinghua University can realize fine burnup calculation and contains complete burnup chain and nuclide information, but it cannot track the fine burnup history. In this paper, we will develop the fine burnup calculation function of PB-HTGR based on NUIT and the fine burnup history of PB-HTGR provided by VSOP, build a burnup analysis process with fine burnup history simulation and fine burnup chain nuclides and realize a burnup uncertainty analysis function. On this basis, the contribution of fission yield uncertainty to the burnup calculation contribution of PB-HTGR is studied, and the results are compared with the VSOP calculation results. The calculation and analysis results show that the fine burnup calculation results based on NUIT and the burnup calculation results based on VSOP are mutually verified, and more nuclide information can be obtained. Such calculation results can be used as a basis for the decay heat uncertainty study of PB-HTGR.

     

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