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首页> 外文期刊>Science, Measurement & Technology, IET >Transient thermal variation in stator winding of nuclear power turbo-generator with the inner sudden water brake
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Transient thermal variation in stator winding of nuclear power turbo-generator with the inner sudden water brake

机译：内突然发生水闸的核电涡轮发电机定子绕组的瞬态热变化

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For nuclear power turbo-generators, the transient thermal variation of its winding and its insulation is one of the important performance indices. For a long time, there have been some occasional accidents at nuclear power stations such as hydrogen and fuel rod leakage. These accidents affect the economy and the safety of people. In this study, a transient temperature variation mechanism of stator winding strands and insulation with a stator water brake has been researched. On account of the stator slot being an open structure, the resistance and reactance are different along the radial direction of the slot. It results in the heat source being different for different strands in the stator slot. The resistance enhancement coefficient of the stator strands is calculated based on the analysis of the eddy-current of magnetic field. A transient fluid-thermal coupled model of a 1000 MW nuclear power turbo-generator stator is established regarding the resistance enhancement coefficient. Calculation results of the insulation temperature are compared with the test data of the turbo-generator that is used at a nuclear power plant.
机译：对于核动力涡轮发电机，其绕组及其绝缘的瞬态热变化是重要的性能指标之一。长期以来，核电站偶尔发生事故，例如氢气和燃料棒泄漏。这些事故影响经济和人民安全。在这项研究中，研究了定子绕组线和定子水制动器绝缘的瞬态温度变化机理。由于定子槽是开放结构，所以电阻和电抗沿槽的径向方向是不同的。这导致定子槽中不同股的热源不同。基于对磁场涡流的分析，计算出定子线束的电阻增强系数。针对电阻增强系数，建立了一个1000 MW核电涡轮发电机定子的瞬态流热耦合模型。将绝缘温度的计算结果与核电站中使用的涡轮发电机的测试数据进行比较。

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