高温气冷堆蒸汽发生器卸压过程模拟和分析

Simulation and Analysis on Pressure Relief Transient of Steam Generator for High Temperature Gas-cooled Reactor

  • 摘要: 当高温气冷堆发生假想事故导致停堆后,堆芯热量将通过冷却系统载出。由于系统设计和蒸汽发生器系统材料等要求,需在冷却水注入前将蒸汽发生器二次侧卸压。本文选用清华大学核能与新能源技术研究院设计的200 MW高温气冷示范堆(HTR-PM),利用热工水力瞬态分析系统程序对其蒸汽发生器二回路系统进行建模,并针对事故后蒸汽发生器不同卸压阀门设计下的热工瞬态过程进行数值模拟,计算和分析了蒸汽发生器换热管等部件在瞬态过程中的温度变化,为相关系统的应力分析和设计提供参考。

     

    Abstract: After a supposed accident leads high temperature gas-cooled reactor to shutdown, the heat from reactor will be removed out by the cooling system. For the 200 MW high temperature gas-cooled reactor (HTR-PM) designed by Institute of Nuclear and New Energy Technology of Tsinghua University, before the cooling water is pumped into the secondary side of steam generator, the pressure relief valve on the live-steam pipeline will open to decrease the secondary side pressure of steam generator. In this paper, a general thermal-hydraulic system analysis code was used for modeling the secondary side of the steam generator of the 200 MW high temperature gas-cooed reactor, and simulating numerically the pressure relief transient after the accident. The temperature of steam generator in the transient with different pressure relief designs was calculated and analyzed, which provides supports for the material stress analysis on steam generator and system design.

     

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