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System dynamics simulation of the thermal dynamic processes in nuclear power plants

机译:核电厂热动力过程的系统动力学模拟

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A nuclear power plant (NPP) is a highly complex system-of-systems as manifested through its internal systems interdependence. The negative impact of such interdependence was demonstrated through the 2011 Fukushima Daiichi nuclear disaster. As such, there is a critical need for new strategies to overcome the limitations of current risk assessment techniques (e.g. the use ofstaticevent and fault tree schemes), particularly through simulation of the nonlineardynamicfeedback mechanisms between the different NPP systems/components. As the first and key step towards developing an integrated NPP dynamic probabilistic risk assessment platform that can account for such feedback mechanisms, the current study adopts a system dynamics simulation approach to model the thermal dynamic processes in: the reactor core; the secondary coolant system; and the pressurized water reactor. The reactor core and secondary coolant system parameters used to develop system dynamics models are based on those of the Palo Verde Nuclear Generating Station. These three system dynamics models are subsequently validated, using results from published work, under different system perturbations including the change in reactivity, the steam valve coefficient, the primary coolant flow, and others. Moving forward, the developed system dynamics models can be integrated with other interacting processes within a NPP to form the basis of a dynamic system-level (systemic) risk assessment tool.
机译:核电厂(NPP)是一个高度复杂的系统体系,通过其内部系统相互依存关系可以看出。 2011年福岛第一核电站灾难证明了这种相互依存的负面影响。因此,迫切需要新的策略来克服当前风险评估技术的局限性(例如使用静态事件和故障树方案),特别是通过模拟不同NPP系统/组件之间的非线性动态反馈机制。作为开发可解释此类反馈机制的集成NPP动态概率风险评估平台的第一步和关键步骤,当前的研究采用系统动力学模拟方法对以下反应堆中的热动力学过程进行建模:二次冷却剂系统;和压水反应堆用于开发系统动力学模型的反应堆堆芯和二次冷却剂系统参数基于帕洛佛得角核电站的参数。随后,使用已发表工作的结果,在不同的系统扰动下,包括反应性的变化,蒸汽阀系数,主要冷却剂流量等,对这三个系统动力学模型进行了验证。展望未来,可以将开发的系统动力学模型与NPP中的其他交互过程集成在一起,以形成动态系统级(系统)风险评估工具的基础。

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