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Quadrature formulas for integral equations of kinetics and digital reactimeters

机译:动力学和数字反应计积分方程的正交公式

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AbstractThe aim of this work is to derive quadrature formulas for nuclear reactor kinetic equations in the form of Volterra integral equations of the second kind and reactimeter equations in the form of integral convolution, the kernel of which is a decay function of delayed neutron precursors (DNP) in the non-group form. The expediency of the transition to integral equationsis caused by the unification of the direct (calculation of power dynamics) and the reverse (calculation of current reactivity) tasks of reactor kinetics. As a result, the solution is reduced to the calculation of the delayed neutrons integral (DNI). This eliminates the source of computational-experimental discrepancies in estimations of reactivity, which is due to the difference in computational algorithms of direct and inverse problems. The paper describes a general scheme for converting different transport equation approximations to describe the contribution of delayed neutrons by means of an integral convolution without using dynamic equations of the DNP concentration. This conversion reduces the model dimension, simplifies the software implementation, eliminates the stiffness problem of differential kinetic equations and provides the stability of calculations. The model dimension is preserved in the case of several fissile nuclides. The integral form of the equations makes it possible to use the experimental decay function in quadrature formulas, which can be identified in the operating conditions of a nuclear reactor and stored pointwise in a nongroup form without decomposition into the sum of exponentials. This eliminates the need to solve the non-linear problem of identifying group parameters of delayed neutrons and increases the adequacy of modeling. A series of quadrature formulas for the calculation of the DNI are obtained and the corresponding algorithms of a digital reactimeter and numerical simulation of the reactor kinetics are described.
机译: 摘要 这项工作的目的是导出第二类Volterra积分方程形式的核反应堆动力学方程的正交公式和第二类Volterra积分方程形式的反应计方程。积分卷积,其内核是非群形式的延迟中子前体(DNP)的衰减函数。积分方程 s 的权宜之计是由于反应堆动力学的直接任务(功率动力学计算)和反向任务(电流反应性计算)的统一引起的。结果,该解被简化为延迟中子积分(DNI)的计算。这样就消除了反应性估算中计算实验差异的根源,这是由于正反问题的计算算法不同而引起的。本文描述了一种通用方案,该方案可以转换积分形式的卷积而不使用DNP浓度的动态方程,从而转换不同的输运方程近似值来描述延迟中子的贡献。这种转换减小了模型尺寸,简化了软件实现,消除了微分动力学方程的刚度问题,并提供了计算的稳定性。在几个裂变核素的情况下,模型尺寸得以保留。方程的积分形式使得可以在正交公式中使用实验衰减函数,该函数可以在核反应堆的运行条件下确定,并以非群形式逐点存储,而不会分解为指数总和。这消除了解决识别延迟中子群参数的非线性问题的需要,并增加了建模的充分性。得到了一系列用于计算DNI的正交公式,并描述了数字电抗器的相应算法以及反应堆动力学的数值模拟。

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