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HEAT TRANSFER TO SUPERCRITICAL WATER (LIQUID-LIKE STATE) FLOWING IN A SHORT VERTICAL BARE TUBE WITH UPWARD FLOW

机译:垂直流向上流动的超临界水(液态)的热传递

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Current Nuclear Power Plants (NPPs) equipped with water-cooled reactors (the vast majority of all NPPs) have relatively low thermal efficiencies within the range of 30-36% compared to those of modern advanced thermal power plants (Supercritical Pressure (SCP) coal-fired - up to 55% thermal efficiency and combined cycle - up to 62%). Therefore, next generation reactors / NPPs should have higher thermal efficiencies close to those of current thermal power plants. Around 60 years ago thermal-power industry has moved from subcritical pressures to SCPs with the major objective to increase thermal efficiency. Based on this proven in power industry experience it was proposed to design Supercritical Water-cooled Reactors (SCWRs), which are one of the six Generation-IV nuclear-reactor concepts under development in selected countries. These days, there are discussions on developing even Small Modular Reactors (SMRs) of SCPs. In spite of a large number of experiments in long bare tubes (pipes) cooled with SCW, developing SCWR concepts requires experimental data in bundle geometries cooled with SCW, which are usually shorter and will have smaller diameters. However, such experiments are extremely complicated and expensive plus each bundle geometry will have a unique Heat-Transfer (HT) characteristics due to various bundle designs. Therefore, as a preliminary and a universal approach -experiments in bare tube of shorter heated lengths and of smaller diameters to match heated lengths and hydraulic-equivalent diameters of fuel bundles are required. Current paper provides experimental data obtained in a short (0.6 m) vertical bare tube of a small diameter (6.28 mm) cooled with upward flow of SCW. Analysis of this dataset is also included. Main emphasis of this research is on liquid-like cooling within the possible conditions of future SCWRs and SCW SMRs. Two HT regimes are encountered at these conditions: 1) Normal HT (NHT) and 2) Deteriorated HT (DHT). Conditions at which the DHT regime appeared are discussed.
机译:与现代先进的火力发电厂(超临界压力(SCP)煤)相比,当前装有水冷反应堆的核电厂(所有核电厂中的绝大多数)的热效率在30-36%的范围内相对较低燃烧-高达55%的热效率和联合循环-高达62%)。因此,下一代反应堆/核电厂应具有比目前的火电厂更高的热效率。大约60年前,热电行业已经从次临界压力转变为SCP,其主要目标是提高热效率。基于在电力行业的经验证明,提议设计超临界水冷堆(SCWR),这是在选定国家中正在开发的六个IV型核反应堆概念之一。如今,关于开发甚至小型SCP的小型模块化反应堆(SMR)的讨论也越来越多。尽管在用SCW冷却的长裸管(管道)中进行了大量实验,但不断发展的SCWR概念仍需要使用SCW冷却的束几何形状的实验数据,通常较短且直径较小。但是,这样的实验极其复杂且昂贵,而且由于束设计多种多样,每个束的几何形状都将具有独特的传热(HT)特性。因此,作为一种初步且通用的方法,需要在裸管中进行较短的加热长度和较小的直径以匹配加热长度和燃料束的水力当量直径的实验。当前的论文提供了在短直径(0.6 m)的垂直裸管中获得的实验数据,该裸管具有小直径(6.28 mm),并通过SCW向上流动进行冷却。该数据集的分析也包括在内。这项研究的主要重点是在未来SCWR和SCW SMR的可能条件下进行类似液体的冷却。在这些条件下会遇到两种HT方案:1)正常HT(NHT)和2)HT恶化(DHT)。讨论了DHT制度出现的条件。

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