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我国第1座超热中子反应堆,其控制和燃料元件效率都很大。如采用常规的添加燃料元件的方法刻度控制元件效率,不仅会干扰堆芯状态,还将超出该反应堆的运行限值和条件的规定,因此,给该堆的安全特性测量带来了困难。介于此,本工作采用了自主研发的数字逆动态反应性计测量技术,其数据处理采用了自动调整步长等先进的数值计算方法,实现了反应性的实时监督,该处理技术经过添加了噪声信号的数学模型的验证、也经过了我国第一座快中子临界装置DF-VI的堆上试验,具有较高的精度。
China’s first superheated neutron reactor, its control and fuel efficiency components are large. Scale control of component efficiency using conventional methods of adding fuel elements not only interferes with the state of the reactor but also outpaces the operational limits and conditions of the reactor and therefore presents difficulties in measuring the safety characteristics of the reactor. In this connection, this work uses a self-developed digital inverse dynamic reactivity meter measurement technology, the data processing using automatic adjustment step and other advanced numerical methods to achieve real-time monitoring of reactivity, the processing technology has been added The verification of the mathematical model of the noise signal has also been tested on the heap of DF-VI, the first fast neutron critical device in China, with high accuracy.