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Theoretical and experimental modelling of a heat pipe heat exchanger for high temperature nuclear reactor technology

机译:高温核反应堆技术用热管换热器的理论和实验模型

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摘要

High temperature heat sources are becoming an ever-increasing imperative in the processing industries for the production of various plastics, fertilisers, coal-to-liquid fuel and hydrogen generation. Current high temperature reactor technology is capable of producing reactor coolant temperatures in excess of 950℃. At these temperatures, tritium which is a radioactive contaminant found in the reactor coolant stream, is able to contaminate the secondary stream by diffusing through the steel retaining wall of the heat exchanger between the reactor coolant and secondary process coolant stream. Current regulations therefore require an extra intermediate heat transfer loop to ensure no cross contamination. A novel heat pipe heat exchanger design is presented which circumvents the need for an intermediate coolant loop. This is done by physically separating the reactor coolant and secondary coolant by two pipe walls and a vapour section and a liquid section. A theoretical transient heat transfer model of such a device is presented. The model uses separate hot gas heating fluid and cold water cooling fluid control volumes, and for the internal working fluid a control volume consisting of a liquid and its vapour in equilibrium with each other. A 2 kW rated experimental model was constructed and tested, using Dowtherm-A as working fluid, to validate the heat pipe heat exchanger theoretical model and design. By determining the boiling heat transfer coefficient through the use of an experimentally formulated correlation it was shown that the theoretical model is indeed able to simulate the characteristic chaotic behaviour, due to the boiling and condensation processes, of the device to within a reasonable level of accuracy. It is concluded that the theoretical simulation model can be used to predict the performance of a higher temperature sodium-charged heat pipe heat exchanger, provided suitable boiling and condensation heat transfer coefficients are used.
机译:在加工业中,用于生产各种塑料,肥料,煤制油燃料和制氢的高温热源正变得越来越重要。当前的高温反应堆技术能够产生超过950℃的反应堆冷却剂温度。在这些温度下,tri是反应堆冷却剂流中发现的放射性污染物,它能够通过在反应堆冷却剂和二次处理冷却剂流之间扩散通过热交换器的钢制挡墙而污染二次流。因此,当前法规要求额外的中间传热回路,以确保没有交叉污染。提出了一种新颖的热管热交换器设计,该设计避免了对中间冷却剂回路的需求。这是通过将反应堆冷却剂和二次冷却剂通过两个管壁以及一个蒸汽段和一个液体段物理分离来完成的。提出了这种装置的理论瞬态传热模型。该模型使用单独的热气加热流体和冷水冷却流体控制体积,对于内部工作流体,使用由彼此平衡的液体及其蒸气组成的控制体积。以Dowtherm-A为工作液,构建并测试了2 kW额定实验模型,以验证热管热交换器的理论模型和设计。通过使用实验公式化的相关性确定沸腾传热系数,结果表明,理论模型确实能够将设备的特征性混沌行为(由于沸腾和冷凝过程而导致)模拟到合理的精度水平内。结论是,只要使用合适的沸腾和冷凝传热系数,理论模拟模型可用于预测高温含钠热管换热器的性能。

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