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首页> 外文期刊>Nuclear Science, IEEE Transactions on >Valuation of Power Oscillations in a BWR After Control Rod Banks Withdrawal Events
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Valuation of Power Oscillations in a BWR After Control Rod Banks Withdrawal Events

机译:控制棒库撤出事件后BWR中功率振荡的评估

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摘要

The out-of-phase mode of oscillation is a very challenging type of instability occurring in BWR (Boiling Water Reactor) and its study is relevant because of the safety implications related to the capability to promptly detect any such inadvertent occurrence by in-core neutron detectors, thus triggering the necessary countermeasures in terms of selected rod insertion or even reactor shutdown. In this work, control rod banks withdrawal transient was considered to study the power instability occurring in a BWR. To simulate this transient, the control rod banks were continuously removed from the BWR core in different cases. The simulation resulted in a very large increase in the power. To perform the instability simulations, the RELAP5/MOD3.3 thermal hydraulic system code was coupled with the PARCS/2.4 3-D neutron kinetic code. Data from a real BWR, the Peach Bottom, have been used as reference conditions and reactor parameters. The trend of the mass flow rate, pressure, coolant temperature and the void fraction to four thermal hydraulic channels symmetrically located in the core with respect to the core centre, were taken. The behavior of the thermal hydraulic parameters investigated presented out-of-phase evolution comparing the channels that represents each half of the core.
机译:异相振荡模式是BWR(沸水反应堆)中发生的一种非常具有挑战性的不稳定类型,其研究是有意义的,因为它与安全性相关,因为它与迅速检测堆芯中子发生任何此类意外事件的能力有关检测器,从而在选择的棒插入甚至反应堆关闭方面触发必要的对策。在这项工作中,考虑了控制棒堆退避瞬变,以研究BWR中发生的功率不稳定性。为了模拟此瞬变,在不同情况下,控制棒束不断从BWR堆芯中取出。仿真导致功率大大增加。为了进行不稳定性模拟,将RELAP5 / MOD3.3热工液压系统代码与PARCS / 2.4 3-D中子动力学代码相结合。来自实际BWR(桃子底部)的数据已用作参考条件和反应堆参数。得出了相对于堆芯中心对称分布在堆芯中的四个热力液压通道的质量流量,压力,冷却液温度和空隙率的趋势。所研究的热工水力参数的行为呈现出异相演变,将代表岩心每半部分的通道进行了比较。

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