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A novel method for in-situ estimation of time constant for core temperature monitoring thermocouples of operating reactors

机译:一种在运反应堆堆芯温度监测热电偶的时间常数原位估计新方法

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Core temperature monitoring system is an important component of reactor protection system in the current generation fast reactors. In this system, multiple thermocouples are housed inside a thermowell of fuel subassemblies. Response time of the thermocouple assembly forms an important input for safety analysis of fast reactor and hence frequent calibration/time constant estimation is essential. In fast reactors the central fuel subassembly is provided with bare fast response thermocouples to detect under cooling events in reactor and take proper safety action. On the other hand, thermocouples in thermowell are mainly used for blockage detection in individual fuel subassemblies. The time constant of thermocouples in thermowell can drift due to creep, vibration and thermal fatigue of the thermowell assembly. A novel method for in-situ estimation of time constant is proposed. This method uses the Safety Control Rod Accelerated Mechanism (SCRAM) or lowering of control Rod (LOR) signals of the reactor along with response of the central subassembly thermocouples as reference data. Validation of the procedure has been demonstrated by applying it to FBTR. (C) 2014 Elsevier B.V. All rights reserved.
机译:堆芯温度监控系统是当前快速反应堆中反应堆保护系统的重要组成部分。在该系统中,多个热电偶装在燃料组件的热套管中。热电偶组件的响应时间是快速反应堆安全分析的重要输入,因此频繁的校准/时间常数估算至关重要。在快速反应堆中,中央燃料组件配备有裸露的快速响应热电偶,以检测反应堆中的冷却事件并采取适当的安全措施。另一方面,热电偶套管中的热电偶主要用于单个燃料子组件中的堵塞检测。热电偶套管中的热电偶的时间常数会因热电偶套管的蠕变,振动和热疲劳而漂移。提出了一种新的时间常数原位估计方法。该方法使用安全控制棒加速机构(SCRAM)或降低反应堆的控制棒(LOR)信号以及中央子组件热电偶的响应作为参考数据。通过将其应用于FBTR,已证明了该程序的有效性。 (C)2014 Elsevier B.V.保留所有权利。

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