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Study on the Numerical Analysis of Nuclear Reactor Kinetics Equations.

机译：核反应堆动力学方程数值分析研究。

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A two-step alternating direction explict method is proposed for the solution of the space-and time-dependent diffusion theory reactor kinetics equations in two space dimensions as a special case of the general class of alternating direction implicit method and the truncation error of this method is estimated. To test the validity of this method it is applied to the Pressurized Water Reactor and CANDU-PHW reactor which have been operating and under construction in Korea. The time dependent neutron flux of the PWR reactor during control rod insertion and time dependent neutronic power of CANDU-PHW reactor in the case of postulated loss of coolant accident are obtained from the numerical calculation results. The results of the PWR reactor problem are shown the close agreement between implicit-difference method used in the TWIGL program and this method, and the results of the CANDU-PHW reactor are compared with the results of improved quasistic method and modal method. (Atomindex citation 13:689707)

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作者
Yang, J. C.;
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年度 1980
页码 1-64
总页数 64
原文格式 PDF
正文语种 eng
中图分类工业技术;
关键词
Reactor Kinetics Equations; Candu Type Reactors; Computer Calculations; Loss of Coolant; Neutron Flux; Numerical Solution; PWR Type Reactors; Reactivity; Reactor Safety; Two-Dimensional Calculations; Foreign technology; ERDA/220100;

机译：反应器动力学方程; Candu型反应器;计算机计算;冷却剂损失;中子通量;数值解; pWR型反应器;反应性;反应堆安全性;二维计算;国外技术; ERDa / 220100;

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1. A 3D nodal mixed dual method for nuclear reactor kinetics with improved quasistatic model and a semi-implicit scheme to solve the precursor equations. [J] . M. Dahmani, A.M. baudron, J.J. Lautard Annals of nuclear energy . 2001,第8期

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2. Numerical solution analysis of fractional point kinetics and heat exchange in nuclear reactor [J] . Tomasz Karol Nowak, Kazimierz Duzinkiewicz, Robert Piotrowski Nuclear Engineering and Design . 2015,第jana期

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4. NUMERICAL SIMULATION FOR NUCLEAR ENGINEERING EDUCATION: A CASE STUDY IN A COURSE 'ADVANCED NUCLEAR REACTOR THERMAL ANALYSIS' [C] . Shanfang Huang, Chao Li, Ruilong Liu, International conference on nuclear engineering . 2018

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Study on the Numerical Analysis of Nuclear Reactor Kinetics Equations.

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