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VOID REACTIVITY (C_(mn)) COEFFICIENTS AS INDICATORS OF BOILING WATER REACTOR STABILITY

机译:无效反应性(C_(mn))系数作为沸水反应堆稳定性的指标

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This paper presents the results of some investigations performed in the area of the stability of Boiling Water Reactors (BWRs). These systems are known to become unstable under certain conditions, and thus the development of different methods for the quantification of their stability properties is of prime importance. Preliminary studies with Reduced Order Models showed that the stability behavior of the system can be described in terms of so-called C_(mn)-coefficients. These coefficients represent the effect of a change in the void fraction on the eigenmodes of a nuclear core. It turned out that when these coefficients are positive, the system is clearly unstable because of the corresponding positive void feedback. On the other hand, in the case of negative C_(mn)-coefficients, it has been found, both using ROMs and dynamic core simulators like SIMULATE-3K, that the system becomes less stable for the C_(mn) coefficients becoming more negative. A thorough examination of the dependence of Decay Ratio on the C_(mn) coefficients using ROMs also demonstrated that there is a strong correlation between the DR and the C_(mn) coefficients what regards the stability properties of a BWR system. As a result, the estimation of the C_(mn) coefficients opens up the possibility of using such coefficients as a qualitative measure of core stability in a predictive manner. This could be used for instance as means to compare the relative stability of several core loadings without the need of running lengthy time-dependent three-dimensional core calculations, and could be of great help to nuclear engineers when designing nuclear cores. Therefore the main purpose of the paper is to investigate the possibility of using C_(mn)-coefficients as an alternative stability indicator for Boiling Water Reactors, as well as to determine their advantages and disadvantages as compared to the traditional Decay Ratio.
机译:本文介绍了在沸水反应堆(BWRs)稳定性方面进行的一些研究的结果。已知这些系统在某些条件下会变得不稳定,因此开发量化其稳定性能的不同方法至关重要。使用降阶模型的初步研究表明,系统的稳定性行为可以用所谓的C_(mn)系数来描述。这些系数表示空隙率变化对核芯本征模的影响。事实证明,当这些系数为正时,由于相应的正空隙反馈,系统显然是不稳定的。另一方面,在C_(mn)系数为负的情况下,已经发现,使用ROM和SIMULATE-3K之类的动态核心模拟器,系统的C_(mn)系数变得更大时变得不稳定。 。使用ROM彻底检查衰减比对C_(mn)系数的依赖性还表明,考虑到BWR系统的稳定性,DR和C_(mn)系数之间存在很强的相关性。结果,对C_(mn)系数的估计开辟了以预测方式将此类系数用作岩心稳定性的定性度量的可能性。例如,这可以用作比较多个堆芯负载的相对稳定性的方法,而无需进行冗长的与时间相关的三维堆芯计算,并且对于设计核芯的核工程师有很大帮助。因此,本文的主要目的是研究使用C_(mn)系数作为沸水反应堆替代稳定性指标的可能性,并确定其与传统衰减比相比的优缺点。

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