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Characteristics Analysis of Supercritical Water-cooled Reactor during Loss of feedwater heatingTransient

机译:给水加热损失超临界水冷堆的特性分析

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The loss of feed-water heating is one of the most important transient and security incidentsfor supercritical water-cooled reactor with needed analysis. Analysis of the relevantparameters is completed during the transient of loss of feed-water heating. The results showthat, the reduced flow of fuel channel will lead to the maximum cladding temperatureincreasing. After the cladding temperature reaches the maximum, it will drop with theincreasing flow of main feed-water. Under the control of the control system, the flow ofmain feed-water rises at the beginning and then begins to drop. As the flow of fuel channeldecreases, the nuclear power will decrease at the start of the transient of loss of feed-waterheating. By the control of control and Monitoring System of Control Rod, power willrebound. Meanwhile, as the heat transfer quantity between the fuel channel and water rodincreases, the flow of moderator in the water rod will increase. So the flow in the fuelchannel will increase at last.
机译:给水加热的损失是超临界水冷堆最重要的瞬态和安全事件之一,需要进行分析。在给水加热损失瞬变期间完成相关参数的分析。结果表明,燃料通道流量的减少将导致最高包层温度的升高。包层温度达到最高温度后,它将随着主给水流量的增加而下降。在控制系统的控制下,主给水流量在开始时上升,然后开始下降。随着燃料通道流量的减少,给水加热损失瞬变的开始,核电将减少。通过控制杆的控制和监视系统的控制,电源将反弹。同时,随着燃料通道与水棒之间的传热量增加,减速剂在水棒中的流量将增加。因此,燃料通道中的流量将最终增加。

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