气冷动力反应堆温度波动的测量

C.P. Greef
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引用次数: 1

摘要

本文介绍了对石墨慢化气冷堆热电偶噪声信号的测量结果。总体调查表明,在所覆盖的频率范围内(高达0.15 Hz),反应堆表现为一个紧密耦合的系统,堆芯不同部分之间没有明显的相位差。在此范围内,温度噪声功率谱可以划分为两个不同的频率区域。在该范围的下半部分,观测到的波动是由于反应堆总功率的波动,而在上半部分是由于传热系数的变化。通过考虑冷却剂和燃料温度之间的传递函数,建立了一个简单的反应堆噪声过程模型并进行了验证。通道气体出口热电偶响应是反应堆故障研究所必需的,通过传统的棒振荡技术和噪声分析测量了固有波动和换料瞬态。结果表明,噪声分析,特别是使用换料瞬态分析,能够取代棒振荡技术。这样做的优点是不干扰反应器的正常运行,减少了实验时间,扩大了测量的频率范围。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Measurements of temperature fluctuations in a gas-cooled power reactor

The results obtained from measurements of thermocouple noise signals from a graphite moderated gas cooled reactor are presented.

An overall survey demonstrated that in the frequency range covered (up to 0·15 Hz), the reactor behaved as a closely coupled system with no significant phase differences between different parts of the core. Furthermore, the temperature noise power spectra could be divided into two distinct frequency regions in this range. In the lower part of the range the observed fluctuations were found to be due to overall reactor power fluctuations, and in the upper part to heat transfer coefficient variations.

A simple model of the noise processes in the reactor has been developed and verified by consideration of the transfer function between coolant and fuel temperatures.

The channel gas outlet thermocouple response, which was required for reactor fault studies, was measured by conventional rod oscillation techniques and noise analysis using both intrinsic fluctuations and refuelling transients. A comparison of the results showed that noise analysis, especially using refuelling transients, was capable of replacing the rod oscillation technique. This gave the advantages of not interfering with the normal operation of the reactor, reducing the experimental time and extending the frequency range of the measurements.

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