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压水堆堆芯双节点模型及其应用

Two-Point Reactor Core Model for Pressurized Water Reactor and Its Application
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摘要 基于节点方法建立双节点反应堆模型,并利用微小摄动理论对模型进行线性化处理,得到双节点线性化反应堆多变量模型;为了更加准确地对棒控系统进行仿真,建立了双节点棒控系统模型。参考AP1000的机械补偿控制策略(MSHIM),在Matlab/Simulink平台上搭建平均温度控制系统和轴向偏移控制系统的仿真程序,并对功率阶跃负荷瞬态工况进行仿真。仿真结果表明,功率偏差始终在目标控制带以内,平均温度和功率水平的实际值与目标值之间存在稳态偏差,偏差处于死区范围之内。因此双节点线性化堆芯模型适用于功率控制系统和功率分布控制系统的仿真和设计。 Based on the nodal method,a two-point core model for pressurized water reactor is developed in this paper.Furthermore,the model is formulated through the linearization of the nonlinear model,and then a Linear Time-Invariant model is obtained.To simulate the control rod system more accurately,a two-point control rod system is built.Referring to the mechanical shim control strategy in AP1000,the average temperature control system and the axial offset control system simulation program are built on the Matlab/Simulink platform and are applied to simulate load transient of step power.The simulation results show that the power derivation remains in the target band,and the steady state deviations between the actual values and target values for the reactor power and mean coolant temperature are in the dead bands.Therefore,the developed model is available for the simulation and design of the power control system and the power distribution control system.
出处 《核动力工程》 EI CAS CSCD 北大核心 2013年第5期6-11,共6页 Nuclear Power Engineering
关键词 反应堆双节点模型 节点方法 堆芯控制 MSHIM Two-point core model Nodal method Reactor core control MSHIM
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参考文献3

  • 1Shimjith S R, Tiwari A P, Naskar M, et al. Space-time Kinetics Modeling of Advanced Heavy Water Reactor for Control Studies[J]. Annals of Nuclear Energy, 2010, 37:310-324.
  • 2Dong Zhe, Xiaojin Huang, Liangju Zhang. A Nodal Dynamic Model for Control System Design andSimulation of an MHTGR Core[J]. Nuclear Engineering and Design, 2010, 240: 1451-1261.
  • 3李海鹏,黄晓津,张良驹.线性化模型在压水堆堆芯系统稳定性分析中的应用[J].核科学与工程,2008,28(4):341-346. 被引量:4

二级参考文献3

  • 1刘豹.现代控制理论:第2版[M].北京:机械工业出版社,2002.
  • 2Adel Ben-Abdennour, Edwards Robert M, Lee Kwang Y. LQG/LTR robust control of nuclear reactors with improved temperature performance [J].IEEE Transac tions on Nuclear Science, 1992, 39 (6), 2286-2294.
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