利用堆芯模拟器OPR1000标定优化功率堆(OPR-1000)控制棒及价值计算

Nguyen An Son, N. Hoa, T. Nguyen, T. Tuan, Osvaldo Camueje Raul
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引用次数: 7

摘要

控制棒是用来改变核反应堆功率的。当然,当堆芯发生紧急情况时,堆芯随时都可能处于亚临界状态并关闭。杆根据其功能分组,并位于核心的不同位置,以最大限度地发挥其功能。实验中采用了两种控制棒标定方法:渐近周期法和棒滴法。在第一种方法中,通过插入待校准的控制棒使反应器达到超临界水平。滴棒法是确定亚临界;在临界状态下,将待校准棒放入堆芯,观察由此产生的中子通量衰减,并将其与反应性联系起来。在本文中,调节棒将根据OPR-1000中的反应性进行校准,该反应性对应于某个控制棒的插入或拔出,而动力堆中的反应性也取决于积分和微分控制棒组。使用核心模拟器OPR1000对这些方法进行测试。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Control Rod Calibration and Worth Calculation for Optimized Power Reactor 1000 (OPR-1000) Using Core Simulator OPR1000
Control rod is used to change the power in nuclear reactor. Certainly, the core at any moment can be made subcritical condition and shut downs when occurring to emergency instance in the core. The rod is grouped based on their function and located at different places in the core where their feature is maximized. Two methods of control rod calibration are the asymptotic period method and the rod-drop method, which were applied in this experiment. In the first method, the reactor is made supcritical by inserting the control rod to be calibrated a certain level. The rod drop method is to determine the subcritical; at the critical state, the rod to be calibrated is dropped into the core, and the resulting decay of neutron flux is observed and related to the reactivity. In this paper, the regulating rod will be calibrated according to the reactivity in OPR-1000 that corresponds to a certain control rod insert or withdraw, and the reactivity in power reactor depends on the integral and differential control rod group too. The core simulator OPR1000 is used to test those methods.
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