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EFFECTS OF ROLLING ON CHARACTERISTICS OF SYSTEM UNDER FORCED CIRCULATION AND NATURAL CIRCULATION

机译:轧制在强制循环和自然循环下系统特性的影响

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The marine nuclear power plant operating in the marine environment has complicated motion under the influence of wind and waves. The movement of marine nuclear power plant will affect the thermal-hydraulic characteristics of its nuclear reactor system. Compared with other typical motion conditions, the effects of rolling conditions on the thermal-hydraulic characteristics of the nuclear reactor system are the most complex. In order to study the effects of rolling conditions on the thermal-hydraulic characteristics of the nuclear reactor system, a thermal-hydraulic system code for motion conddions named STAC was developed. The STAC code was verified by the experiments conducted in Japan. The effects of rolling conditions on the thermal-hydraulic characteristics of the nuclear reactor system under forced circulation and natural circulation are studied with the STAC code. The simulation results show that the thermal parameters of the reactor system under rolling condition fluctuate periodically. The fluctuation period of the thermal parameters of the core is half of the rolling period, and the fluctuation periods of other thermal parameters are the same as the rolling period. The effect of rolling condition on thermal-hydraulic parameters under forced circulation is smaller than that under natural circulation. The fluctuation amplitudes of the thermal parameters increase with the angle amplitude of the rolling condition. There is a rolling period with the smallest fluctuation amplitude. Under the rolling condition with short period, the fluctuation amplitudes of the thermal parameters increase and their average values change rapidly as the rolling period decreases. Under the rolling condition with large period, the fluctuation amplitudes of the thermal parameters increase with the rolling period, and they tend to fixed values.
机译:在海洋环境中运行的海洋核电站在风和波浪的影响下具有复杂的动作。海洋核电站的运动将影响其核反应堆系统的热液压特性。与其他典型的运动条件相比,轧制条件对核反应堆系统热液压特性的影响是最复杂的。为了研究滚动条件对核反应堆系统热液压特性的影响,开发了名为Stac的运动支护的热液压系统代码。 STAC代码由日本进行的实验验证。用Stac代码研究了滚动条件对强制循环和自然循环的核反应堆系统热液压特性的影响。仿真结果表明,轧制条件下反应器系统的热参数周期性地波动。核心的热参数的波动时段是滚动周期的一半,其它热参数的波动周期与滚动时段相同。强制循环下轧制条件对热液压参数的影响小于天然循环下的热液压参数。热参数的波动幅度随着轧制状态的角度幅度而增加。有一个具有最小波动幅度的滚动周期。在短时间内的轧制条件下,随着滚动周期降低,热参数的波动幅度和其平均值迅速变化。在具有大时段的轧制条件下,热参数的波动幅度随滚动周期而增加,并且它们倾向于固定值。

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