共查询到17条相似文献,搜索用时 171 毫秒
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在核电计算中,核岛中的反应堆动态学方程和常规岛中的湿蒸汽汽轮机甩负荷时各级压力变化方程都是典型的刚性常微分方程。本文介绍用通用性强的Gear方法求解这些刚性方程的有效性。在解点堆动态学方程时,Gear方法的计算效率与分段多项式逼近法相当;在对矩阵求逆的算法作了改进后,该方法的计算效率就高于分段多项式逼近法。 相似文献
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求解反应堆动态方程的插值多项式法 总被引:7,自引:2,他引:7
本文利用三阶 Hermite 插值多项式法求解点堆动态方程,衰变热方程和反应性反馈方程。由于考虑了反应堆连续运行史对衰变热的影响,所给出的公式可精确计算反应堆运行瞬态和停堆后剩余功率随时间的变化。对例题的核算表明,上述方法允许很大的时间步长并保证很高的计算精度。 相似文献
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求解点堆中子动力学方程的三角插值法 总被引:1,自引:1,他引:0
在求解点堆中子动力学方程组中,对中子密度N(t)使用三角函数近似方法,并使用全隐式格式保证A稳定性,给出一个求解的方法。计算结果表明,此方法可以灵活应用于各种反应性输入,计算时间短,计算精度较高,可以满足实际工程的需要,是求解点动态方程的一种较好方法。 相似文献
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由于点堆中子动力学方程是个刚性方程,因此准确、快速、稳定地求解方程是困难的。得益于现代计算机技术的进步,本文直接采用代中子时间计算法求解点堆中子动力学方程,并用C++语言编制了计算程序。经过基准例题和动态-逆动态对比计算,验证了模型、程序计算的准确性和稳定性,而计算时间也是可接受的。 相似文献
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描述了快堆燃耗计算程序NDHEXB的理论模型,并给出了中国实验快堆(CEFR)的计算结果。结果表明NDHEXB具有良好的计算效率与精度。在NDHEXB程序中,采用六角形几何下的节块展开法求解中子扩散方程,利用常微分方程的一种数值方法——梯形法求解燃耗方程。 相似文献
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Abdallah A. Nahla 《Nuclear Engineering and Design》2010,240(6):1622-1629
New analytical solution for solving the point reactor kinetics equations with multi-group of delayed neutrons is presented. This solution is based on the roots of inhour equation, eigenvalues of the coefficient matrix. The inhour equation presents in new sample formula. The analytical solution represents the exact analytical solution for the point kinetics equations of multi-group of delayed neutrons with constant reactivity. Also, it represents the accurate solution for solving the point kinetics equations of multi-group of delayed neutrons with ramp and temperature feedback reactivities. This method are applied to different types of reactivity and compared to the traditional methods. 相似文献
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Point kinetics equations are stiff differential equations, and their solution by the conventional explicit methods will give a stable consistent result only for very small time steps. Since the neutron lifetime in a LMFBR is very short, the point kinetics equations for LMFBRs become even stiffer. In this study the power series solution (PWS) method is applied for solving the point kinetics equations for a typical LMFBR. A Fortran program is developed for accident analysis of LMFBRs with the PWS method for solving the point kinetics and a lumped model for solving the heat transfer equations. A new technique is developed with fixing factor to find out the average temperature at the peak power node (PPN) without performing temperature calculations at all axial nodes in a reactor fuel pin. The temperature at PPN also decides whether the reactor is within the design safety limit (DSL) or it has entered a serious transient that may lead to an accident. The coupled heat transfer and point kinetics models for a peak power node give the average fuel, clad and coolant temperatures. For the transient over power accidents (TOPA), this is the best way for calculating the temperature, with minimum amount of computations. TOPA analyses are carried out with PWS method. It is found that the PWS methodology uses a small number of numerical operations, while the computational time and the accuracy are comparable with the available fast computational tools. This methodology can be used in nuclear reactor simulation studies and accident analysis. 相似文献
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《核技术(英文版)》2016,(1):170-177
The stochastic point kinetics equations with a multi-group of delayed neutrons, which are the system of a couple of stiff stochastic differential equations, are presented.The analytical exponential model is used to solve the stochastic point kinetics equations in the dynamical system of the nuclear reactor. This method is based on the eigenvalues and corresponding eigenvectors of the coefficient matrix. The analytical exponential model calculates the mean and standard deviations of neutrons and precursor populations for the stochastic point kinetics equations with step, ramp, and sinusoidal reactivities.The results of the analytical exponential model are compared with published methods and the results of the deterministic point kinetics model. This comparison confirms that the analytical exponential model is an efficient method for solving stochastic stiff point kinetics equations. 相似文献
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Yasser Mohamed Hamada 《Nuclear Engineering and Design》2011,241(8):3032-3041
Based on the power series method (PWS), a generalized power series method (GPWS) has been introduced for solving the point reactor kinetics equations. The stiffness of the kinetics equations restricts the time interval to a small increment, which in turn restricts the PWS method within a very small constant step size. The traditional PWS method has been developed using a new formula that can control the time step at each step while transient proceeds. Two solvers of the PWS method using two successive orders have been used to estimate the local truncation errors. The GPWS method has employed these errors and some other constraints to produce the largest step size allowable at each step while keeping the error within a specific tolerance. The proposed method has resolved the stiffness point kinetics equations in a very simple way with step, ramp and zigzag ramp reactivities. The generalized method has turned out to represent a fast and accurate computational technique for most applications. The method is seemed to be valid for a time interval that is much longer than the time interval used in the conventional numerical integration, and is thus useful in reducing computing time. The method constitutes an easy-to-implement algorithm that provides results with high accuracy for most applications where, the reactor kinetics equations are reduced to a differential equation in a matrix form convenient for explicit power series solution. Results obtained by GPWS method: attest the power of the theoretical analysis, they demonstrate that the convergence of the iteration scheme can be accelerated, and the resulting computing time can be greatly reduced while maintaining computational accuracy. The point kinetics equations have been solved as a preliminary simple case aimed at testing the applicability of the GPWS method to solve point kinetics equations with feedback or, space kinetics problems. 相似文献
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The point reactor kinetics model is a stiff system of linear/nonlinear ordinary differential equations. In fact, the numerical solutions of this stiff model need a smaller time step intervals within various computational schemes. The aim of this work is an accurate numerical solution without need to the smaller time step intervals. Theta method is the most popular, simplest and widely used method for solving the first order ordinary differential equations. In light of this fact, theta method is treated for solving the matrix form of this model via the eigenvalues and corresponding eigenvectors of the coefficient matrix. In this work, the matrix form of the stiff point kinetics equations with multi-group of delayed neutrons is introduced. The treatment theta method is applied to solve the stiff point kinetics equations with six groups of delayed neutrons. The performance of the treatment theta method is evaluated in several case studies involving step, ramp, sinusoidal and pulse reactivities. The results of the treatment theta method are more accurate than the theta method comparing with the conventional methods. 相似文献
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The point reactor kinetics equations of multi-group of delayed neutrons in the presence Newtonian temperature feedback effects are a system of stiff nonlinear ordinary differential equations which have not any exact analytical solution. The efficient technique for this nonlinear system is based on changing this nonlinear system to a linear system by the predicted value of reactivity and solving this linear system using the fundamental matrix of the homogenous linear differential equations. The nonlinear point reactor kinetics equations are rewritten in the matrix form. The solution of this matrix form is introduced. This solution contains the exponential function of a variable coefficient matrix. This coefficient matrix contains the unknown variable, reactivity. The predicted values of reactivity in the explicit form are determined replacing the exponential function of the coefficient matrix by two kinds, Backward Euler and Crank Nicholson, of the rational approximations. The nonlinear point kinetics equations changed to a linear system of the homogenous differential equations. The fundamental matrix of this linear system is calculated using the eigenvalues and the corresponding eigenvectors of the coefficient matrix. Stability of the efficient technique is defined and discussed. The efficient technique is applied to the point kinetics equations of six-groups of delayed neutrons with step, ramp, sinusoidal and the temperature feedback reactivities. The results of these efficient techniques are compared with the traditional methods. 相似文献
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克服点堆中子动力学方程刚性的新方法—端点浮动法 总被引:2,自引:0,他引:2
点堆中子动力学方程是一个刚性微分方程,本文提出一个简洁有效地克服点堆中子动力学方程刚性的方法——端点浮动法。该方法采用端点浮动,用少量多项式来分段近似积分中的中子密度,并采用全隐离散格式,以有效地克服刚性,从而保证解的必要精度。根据几种实例的验算证明:该方法是有效可靠的,时间步长不受最大(绝对值)负时间常数的限制,而计算公式简单,便于使用。 相似文献