VVER 1000 Pressurizer System and Control Modelling in Dymola

Anna Fortová, Filip Ježek
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引用次数: 2

Abstract

The pressurizer is responsible for controlling the pressure and temperature in the primary circuit of the nuclear power plant. It is basically a pressure vessel, filled partially with water and partially with steam at saturation state. The controlling process can be described by two regimes, either by the self-control regime or by the automatic control regime. This paper is describing the simplified automatic control regime on the model of the pressurizer in the primary circuit of VVER 1000 made in Dymola software with the ClaRa library. Reactor power change and corresponding steam generator power change are the actuators in the simulation. The behaviour of the coolant level and pressure in the pressurizer is simulated in the model and it is then compared with data provided by the supplier of VVER 1000.
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vver1000稳压器系统与控制建模
稳压器负责控制核电站一次回路的压力和温度。它基本上是一个压力容器,部分充满了水,部分充满了饱和状态下的蒸汽。控制过程可以用两种状态来描述,即自我控制状态或自动控制状态。本文描述了用Dymola软件用ClaRa库制作的VVER 1000一次回路稳压器模型的简化自动控制机制。反应堆功率变化和相应的蒸汽发生器功率变化是仿真中的执行器。该模型模拟了稳压器内冷却液液位和压力的变化,并与VVER 1000供应商提供的数据进行了比较。
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