反应堆控制棒在事故工况下的落棒时间分析
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摘要
反应堆控制棒在事故工况下的落棒时间分析方法,主要是建立驱动线上各部件在外力作用下的强迫振动方程和控制棒在垂直方向上的落棒运动方程。通过考虑落棒过程中控制棒与外侧部件之间的碰撞效应,将上述两个方程联系起来。用有限差分法对振动方程作离散,对时间历程则用Wilson-θ法逐步进行分析,对由碰撞所引起的非线性采用修正的Newton法作迭代处理。利用已有的试验结果考核计算方法的正确性和可靠性。理论考题以及与试验结果的比较表明,以上述方法为基础编制的分析程序是适用、可靠的。它为相关部件的分析法设计和安全分析提供了有效手段。
The computational method of reactor control rod drop time under accident conditions lies mainly in establishing forced vibration equations for the components under action of outside forces on control rod driven line and motion equation for the control rod moving in vertical direction. The above two kinds of equations are connected by considering the impact effects between control rod and its outside components. Finite difference method is adopted to make discretization of the vibration equations and Wilson-o method is applied to deal with the time history problem. The non-linearity caused by impact is iteratively treated with modified Newton method. Some experimental results are used to validate the validity and reliability of the computational method. Theoretical and experimental testing problems show that the computer program based on the computational method is applicable and reliable. The program can act as an effective tool of design by analysis and safety analysis for the relevant components.
The computational method of reactor control rod drop time under accident conditions lies mainly in establishing forced vibration equations for the components under action of outside forces on control rod driven line and motion equation for the control rod moving in vertical direction. The above two kinds of equations are connected by considering the impact effects between control rod and its outside components. Finite difference method is adopted to make discretization of the vibration equations and Wilson-o method is applied to deal with the time history problem. The non-linearity caused by impact is iteratively treated with modified Newton method. Some experimental results are used to validate the validity and reliability of the computational method. Theoretical and experimental testing problems show that the computer program based on the computational method is applicable and reliable. The program can act as an effective tool of design by analysis and safety analysis for the relevant components.
引文
1 Morrone A. Scram and nonlinear reactor system seismic analysis for a liquid metal fast reactor. Proc. 3rd SMiRT K 8/4． London 1975
2 藤田胜久等.地震时压水堆控制棒的插入特性,日本机械学会论文集(C篇).Vol.53(日文),1987,5
3 Castoldi A, Casirati M, Zola M. Problems of Experimental Seismic Test of a Safety Rod Mechanism(MAB). Proc. 6th SMiRT. K11/4 Paris, 1981
4 Castoldi A, Franchioni G, Zola M. Experimental Demonstration of the PEC Fast Reactor Scramability in the Case of Earthquake. Proc. 8th SMiRT. EK 2/7． Brussels, 1985
5 Borsoi L, Canteneur C, Berthevas G. Computation of control rod drop under seismic conditions. Proc. 14th SMiRT J07/1． Lyon, 1997
6 Dou Y, Yao W, Jiang N, et al. A scram analysis under accident conditions for a reactor control rod system. Proc. 14th SMiRT J07/7． Lyon, 1997
7 Timoshenko S, D. H. Young , W. Weaver, Jr. Vibration Problem in Engineering, 4th ed. John Wiley ＆ Sons, Inc., 1974
8 Yang R, Lu L, Shao Y, et al. Seismic qualification test report for CRDM of PC project. SNERDI Technical Report. 1996
2 藤田胜久等.地震时压水堆控制棒的插入特性,日本机械学会论文集(C篇).Vol.53(日文),1987,5
3 Castoldi A, Casirati M, Zola M. Problems of Experimental Seismic Test of a Safety Rod Mechanism(MAB). Proc. 6th SMiRT. K11/4 Paris, 1981
4 Castoldi A, Franchioni G, Zola M. Experimental Demonstration of the PEC Fast Reactor Scramability in the Case of Earthquake. Proc. 8th SMiRT. EK 2/7． Brussels, 1985
5 Borsoi L, Canteneur C, Berthevas G. Computation of control rod drop under seismic conditions. Proc. 14th SMiRT J07/1． Lyon, 1997
6 Dou Y, Yao W, Jiang N, et al. A scram analysis under accident conditions for a reactor control rod system. Proc. 14th SMiRT J07/7． Lyon, 1997
7 Timoshenko S, D. H. Young , W. Weaver, Jr. Vibration Problem in Engineering, 4th ed. John Wiley ＆ Sons, Inc., 1974
8 Yang R, Lu L, Shao Y, et al. Seismic qualification test report for CRDM of PC project. SNERDI Technical Report. 1996
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