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State change modal method for numerical simulation of dynamic processes in a nuclear reactor

机译:用于核反应堆动态过程数值模拟的状态变化模态方法

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Modeling of dynamic processes in nuclear reactors is carried out, mainly, on the basis of the multigroup diffusion approximation for the neutron flux. The basic model includes a multidimensional set of coupled parabolic equations and ordinary differential equations. Dynamic processes are modelled by a successive change of the reactor states, which are characterized by given coefficients of the equations. In the modal method, the approximate solution is represented as an expansion on the first eigenfunctions of some spectral problem. The numerical-analytical method is based on the use of the dominant time-eigenvalues of a multigroup diffusion model taking into account delayed neutrons. In this work the application of the modal methodology based on calculation of the dominant eigenvalues and eigenfunctions of alpha-eigenvalue problem has been tested for the VVER-1000 reactor test model. The last is characterized by the fact that some eigenvalues are complex. Reactor dynamics behavior is simulated for symmetrical and non-symmetrical control rods insertion/withdrawal. The power calculation results obtained with the modal method were compared with the numerical solution of the dynamics problem. A rather good agreement was shown for the problem with single delayed neutron precursor group.
机译:核反应堆动态过程的建模主要是基于中子通量的多组扩散近似进行的。基本模型包括耦合的抛物线方程和常微分方程的多维集。动态过程是通过连续改变反应堆状态来建模的,反应堆状态的变化以给定的方程系数为特征。在模态方法中,近似解表示为某个频谱问题的第一本征函数的展开。数值分析方法基于多组扩散模型的主要时间特征值的使用,其中考虑了延迟中子。在这项工作中,已经针对VVER-1000反应堆测试模型测试了基于主要特征值和特征值特征函数计算的模态方法的应用。最后一个特征是某些特征值很复杂。针对对称和非对称控制棒的插入/抽出,模拟了反应堆动力学行为。将模态方法获得的功率计算结果与动力学问题的数值解进行了比较。对于单个延迟中子前体群的问题显示出相当好的协议。

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