【摘要】 研究了压水堆核电站主回路系统的模型化问题,提出了适应于微型计算机仿真的核电站系统程序。文章将核电站主系统划分为五大模块分别建立数学模型:堆芯中子动力学模块采用点堆动力学模型;堆芯和燃料模块采用一维分布参数模型;稳压器模块采用三区不平衡模型;U型管蒸汽发生器模块采用具有可动边界点的漂移流模型;管道模块采用集总参数模型。然后根据控制容积法思想,运用中心差分法对所提出的数学模型作空间离散化处理,得到以时间为自变量的有关状态参数的微分方程组。选用吉尔方法求解刚性微分方程组的初值问题。编制了相应的微型计算机程序DYSONP。并以H. B. Ronbinson压水堆核电站为例,对电站甩负荷、蒸汽发生器蒸汽排放阀误动作和蒸汽发生器传热管道破裂三类事故的20余种工况下的瞬态安全问题进行了分析。计算表明,所得计算结果与大型程序RELAP5的相应仿真曲线基本一致,并与有关试验数据符合良好。更多还原

【Abstract】 The modeling of PWR nuclear power plant main circuit system has been researched in this paper, and the plant transient safety analyses have been carried out on microcomputers. In this model, the neutron dynamic and thermohydrodynamie behavior of the reactor core is discribed by point kinetic model and an one-dimension distributed parameter model respectively. A nonequalibrium three regions pressurzer model and a two phase drift flux steam generator model as well as lumped parameter pipe models are adopted. After space discretization by central difference, the numerical initial value problem with stiff ordinary differential equations is solved by the Gear method. Simulating results are presented for three kinds of transients (i. e plant trip transient,three steam dump valves fail open transient and steam generator tube repture transient) by applying the program DYSONP relevant to the model. The results agree well with the corresponding results of the code RELAP5 or experimental data obtained on the H. B. Robinson Unit 2 Power Plant.更多还原