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首页> 外文期刊>International journal of nuclear desalination >Dynamics of reverse osmosis in a standalone cogenerative nuclear reactor (Part Ⅱ: load changes)
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Dynamics of reverse osmosis in a standalone cogenerative nuclear reactor (Part Ⅱ: load changes)

机译：独立的蓄热式核反应堆的反渗透动力学（第二部分：负荷变化）

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The coupling of desalination units with nuclear power plants has been studied in the present work - in this respect, the dynamic behaviour of the pressurised water reactor safety features, represented by the integrity of the fuel cladding, under some transient cases caused by secondary circuit load changes. A cosine-shaped heating through the reactor fuel is taken with its corresponding coolant lumps, to simulate realistic cases encountered in nuclear reactors. As an example, the mathematical model for the Westinghouse 3411 MWth pressurised water reactor, a familiar design with widely published design data was developed. The model consists of two parts; the first one is concerned with the dynamics of the primary side of the reactor; and the second, with the secondary side of the plant. To study the dynamics of the reactor, a 17-lumped parameters model was used. This is a first-order differential equation deduced from the first principles considering six groups of delayed neutrons. A computer program was developed using the Runge-Kutta method to solve these equations and to predict the behaviour of the state variables with time. Two case studies were considered as examples for normal transients. The developed model, which describes the dynamic response of the reactor, primary circuit and secondary circuit, has been analysed and verified with the relevant models. The first case, represented in Part 1 of this study, is concerned with the effect of changes of primary side transient reactivity, including the movement of the reactor control rods. The second one, represented in Part 2 of this study, considers the effect of the secondary side transient reactivity, as the load changes, on the system behaviour. As an example for the secondary side transient, load perturbations, such as load variations in standalone RO desalination units, are selected to study the effect of changing the secondary side conditions on the plant behaviour. The results showed that the reactor components and the fuel matrix should not be affected, and the fuel-cladding integrity is maintained within the safe limits, in all scram cases of RO desalination units coupled with nuclear power plants in the case of either a planned shutdown or an accidental shutdown.
机译：在当前工作中已经研究了海水淡化装置与核电厂的耦合-在这方面，在二次回路负载引起的某些瞬态情况下，压水堆安全特征的动态行为，以燃料包壳的完整性为代表。变化。通过反应堆燃料的余弦形加热及其相应的冷却剂块，以模拟核反应堆中遇到的实际情况。例如，针对西屋3411兆瓦时压水反应堆的数学模型，开发了一个熟悉的设计并广泛发布了设计数据。该模型包括两个部分：第一个涉及反应堆初级侧的动力学；第二个是工厂的次级侧。为了研究反应堆的动力学特性，使用了一个17集总参数模型。这是一阶微分方程，是根据第一原理推导的，其中考虑了六组延迟中子。使用Runge-Kutta方法开发了一个计算机程序来求解这些方程式，并预测状态变量随时间的行为。考虑了两个案例研究作为正常瞬态的示例。描述了反应堆，一次回路和二次回路的动态响应的已开发模型已经过相关模型的分析和验证。在本研究的第1部分中代表的第一种情况与一次侧瞬态反应性变化的影响有关，包括反应堆控制棒的移动。在本研究的第2部分中，第二篇文章讨论了负载变化时次级侧瞬态反应性对系统性能的影响。作为次级侧瞬变的一个示例，选择负载扰动（例如独立的RO脱盐装置中的负载变化）来研究改变次级侧条件对工厂性能的影响。结果表明，在计划关闭的所有RO淡化装置加核电站的紧急情况下，反应堆组件和燃料基体均不受影响，燃料包壳完整性保持在安全范围内或意外关机。

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