Development of a linearized model of a pressurized water reactor generating station for power system dynamic simulations

Samet E. Arda, K. Holbert, J. Undrill
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引用次数: 9

Abstract

A pressurized water reactor (PWR) nuclear power plant (NPP) model is introduced into Positive Sequence Load Flow (PSLF) software in order to evaluate the load-following capability of NPPs. The nuclear steam supply system (NSSS) consists of a reactor core, hot and cold legs, plenums, and a U-tube steam generator. The physical systems listed above are represented by mathematical models utilizing a state variable lumped parameter approach. A steady-state control program for the reactor, and simple turbine and governor models are also developed. Subsequently, the NSSS representation is incorporated into PSLF and coupled with built-in excitation system and generator models. Different simulation cases are run when sudden loss of generation occurs in a power system which includes hydroelectric and natural gas power plants besides the developed PWR NPP. The effect of the load-following operational mode on the key variables of the NSSS is observed.
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用于电力系统动态仿真的压水堆电站线性化模型的建立
为了评价压水堆核电厂的负荷跟随能力,将压水堆核电厂模型引入正序负荷流(PSLF)软件中。核蒸汽供应系统(NSSS)由反应堆堆芯、热腿和冷腿、全气室和u型管蒸汽发生器组成。上面列出的物理系统由利用状态变量集总参数方法的数学模型表示。还开发了反应器的稳态控制程序,以及简单的涡轮和调速器模型。随后,将NSSS表示并入PSLF,并与内置励磁系统和发电机模型耦合。在已开发的压水堆核电站之外,还包括水电和天然气电厂在内的电力系统中,对发生突然发电损失的情况进行了不同的仿真。观察了载荷跟随运行模式对非稳态稳态系统关键变量的影响。
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