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首页> 外文期刊>Communications in Nonlinear Science and Numerical Simulation >Development and analysis of some versions of the fractional-order point reactor kinetics model for a nuclear reactor with slab geometry
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Development and analysis of some versions of the fractional-order point reactor kinetics model for a nuclear reactor with slab geometry

机译:具有平板几何形状的核反应堆分数阶反应堆动力学模型的某些版本的开发和分析

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摘要

In this paper, we report the development and analysis of some novel versions and approximations of the fractional-order (FO) point reactor kinetics model for a nuclear reactor with slab geometry. A systematic development of the FO Inhour equation, Inverse FO point reactor kinetics model, and fractional-order versions of the constant delayed neutron rate approximation model and prompt jump approximation model is presented for the first time (for both one delayed group and six delayed groups). These models evolve from the FO point reactor kinetics model, which has been derived from the FO Neutron Telegraph Equation for the neutron transport considering the subdiffusive neutron transport. Various observations and the analysis results are reported and the corresponding justifications are addressed using the subdiffusive framework for the neutron transport. The FO Inhour equation is found out to be a pseudo-polynomial with its degree depending on the order of the fractional derivative in the FO model. The inverse FO point reactor kinetics model is derived and used to find the reactivity variation required to achieve exponential and sinusoidal power variation in the core. The situation of sudden insertion of negative reactivity is analyzed using the FO constant delayed neutron rate approximation. Use of FO model for representing the prompt jump in reactor power is advocated on the basis of sub-diffusion. Comparison with the respective integer-order models is carried out for the practical data. Also, it has been shown analytically that integer-order models are a special case of FO models when the order of time-derivative is one. Development of these FO models plays a crucial role in reactor theory and operation as it is the first step towards achieving the FO control-oriented model for a nuclear reactor. The results presented here form an important step in the efforts to establish a step-by-step and systematic theory for the FO modeling of a nuclear reactor.
机译:在本文中,我们报告了具有平板几何形状的核反应堆的分数阶(FO)点反应堆动力学模型的一些新颖版本和近似值的开发和分析。首次提出了FO Inhour方程,逆FO点反应堆动力学模型以及恒定延迟中子速率近似模型和快速跳跃近似模型的分数阶版本的系统开发(一个延迟组和六个延迟组) )。这些模型是从FO点反应堆动力学模型演化而来的,该模型已从FO中子电报方程式导出,其中考虑了次扩散中子输运。报告了各种观察和分析结果,并使用了中子输运的亚扩散框架解决了相应的理由。发现FO Inhour方程是一个伪多项式,其阶数取决于FO模型中分数导数的阶数。导出了反FO点反应器动力学模型,并将其用于寻找实现堆芯指数和正弦功率变化所需的反应性变化。使用FO常数延迟中子速率近似分析负反应性突然插入的情况。在子扩散的基础上,提倡使用FO模型来表示反应堆功率的迅速跃升。对于实际数据,与各个整数阶模型进行了比较。而且,从分析上已经表明,当时间导数的阶次为1时,整数阶模型是FO模型的特例。这些FO模型的开发在反应堆理论和操作中起着至关重要的作用,因为这是实现面向核反应堆的FO控制导向模型的第一步。本文介绍的结果构成了建立逐步的系统理论以进行核反应堆的FO模拟的重要一步。

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