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Implementing a pressurized water reactor nuclear power plant model into grid simulations

机译:将压水堆核电站模型应用于电网仿真

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A pressurized water reactor (PWR) nuclear power plant model (NPP) representing one unit of the Palo Verde Nuclear Power Generating Station is incorporated into Positive Sequence Load Flow (PSLF) software. The nuclear steam supply system (NSSS) model comprises a point kinetics description of neutronics and thermodynamics in the reactor core, pressurizer, plenums, hot and cold legs. In addition, the PWR considered here utilizes a recirculation (U-tube) steam generator. A sliding-average-temperature control program for the reactor, pressurizer pressure controller, and simple turbine and governor models are also developed. Subsequently, the NSSS representation is implemented into PSLF by user-defined modeling. Simulation results of isolated plant for a step change in reactivity due to control rod withdrawal are presented and then effect of a disturbance in the medium-sized power system on the developed model of NPP is evaluated.
机译:代表帕洛佛得角核电站一个单元的压水堆(PWR)核电站模型(NPP)已合并到“正序潮流”(PSLF)软件中。核蒸汽供应系统(NSSS)模型包括反应堆堆芯,增压器,气室,冷热管中的中子学和热力学的点动力学描述。另外,此处考虑的压水堆利用了再循环(U型管)蒸汽发生器。还开发了反应堆,增压器压力控制器以及简单的涡轮和调速器模型的滑动平均温度控制程序。随后,通过用户定义的建模将NSSS表示实现为PSLF。给出了由于控制棒抽出而导致反应性发生阶跃变化的孤立工厂的仿真结果,然后评估了中型电力系统中的扰动对已开发的NPP模型的影响。

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