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Volume 44 Issue 4
Aug.  2023
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Gu Zhixing, Yu Hongxing, Huang Daishun, Yan Mingyu, Shen Yaou, Feng Wenpei, Gong Zhengyu. Development and Verification of 3D Code for Steam Generator Tube Rupture Accident of LBE-cooled Reactor[J]. Nuclear Power Engineering, 2023, 44(4): 226-233. doi: 10.13832/j.jnpe.2023.04.0226
Citation: Gu Zhixing, Yu Hongxing, Huang Daishun, Yan Mingyu, Shen Yaou, Feng Wenpei, Gong Zhengyu. Development and Verification of 3D Code for Steam Generator Tube Rupture Accident of LBE-cooled Reactor[J]. Nuclear Power Engineering, 2023, 44(4): 226-233. doi: 10.13832/j.jnpe.2023.04.0226

Development and Verification of 3D Code for Steam Generator Tube Rupture Accident of LBE-cooled Reactor

doi: 10.13832/j.jnpe.2023.04.0226
  • Received Date: 2023-04-12
  • Rev Recd Date: 2023-05-30
  • Publish Date: 2023-08-15
  • Steam Generator Tube Rupture (SGTR) accident is one of the significant safety problems that must be considered in the design of Lead-Bismuth-Eutectic (LBE) cooled reactor. With respect to the SGTR in LBE-cooled reactor, and to cope with the challenges of 3D propagation of pressure waves and 3D migration of water steam under the complex geometric structures, the three-dimensional numerical model and algorithm of the interaction between LBE and water were studied based on the Euler hydrodynamic theory of multiphase flow, and a special code was developed. The code was verified by means of experimental comparison and code-to-code comparison, and the verification results were in good agreement. It is demonstrated that the numerical theories and models used in this paper are suitable for describing the "LBE-water" interaction during SGTR accidents in LBE-cooled reactors. And the 3D code developed in this paper has important potential application values in coping with the 3D evolution processes of SGTR accidents in LBE-cooled reactors under the complex geometric structures, including the pressure wave propagation and steam migration. The research achievements in this paper are expected to provide strong supports for the SGTR accident analyses of LBE-cooled reactors in China.

     

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