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Volume 39 Issue S1
Aug.  2018
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Zeng Chang, Zhao Yu, Ye Zhu, Ren Yun. Simulation and Analysis of Reactor Coolant System for Two-Loop Nuclear Power Plant[J]. Nuclear Power Engineering, 2018, 39(S1): 58-61. doi: 10.13832/j.jnpe.2018.S1.0058
Citation: Zeng Chang, Zhao Yu, Ye Zhu, Ren Yun. Simulation and Analysis of Reactor Coolant System for Two-Loop Nuclear Power Plant[J]. Nuclear Power Engineering, 2018, 39(S1): 58-61. doi: 10.13832/j.jnpe.2018.S1.0058

Simulation and Analysis of Reactor Coolant System for Two-Loop Nuclear Power Plant

doi: 10.13832/j.jnpe.2018.S1.0058
  • Received Date: 2018-04-22
  • Rev Recd Date: 2018-07-11
  • Available Online: 2025-02-09
  • The reactor coolant system simulation model for the two-loop nuclear power plant is established using the thermal hydraulic analysis software Flowmaster. The power operation steady condition, the bias-loop operation steady condition during startup/shutdown reactor, the pump coastdown operation transient condition after loss of off-site power are simulated. The results show that the simulation data matches well with the design values and actual operation values, and the deviations are less than 4%. The simulation model provides a reference for the design optimization and operation of the subsequent reactors of the same type.

     

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