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通过对角管式蒸汽锅炉侧墙水冷壁的循环原理进行分析,找到了影响再循环管水动力特性的主要因素,并建立了水动力特性实验台,对热负荷和预分离集箱影响再循环管作用的规律了实验研究。 相似文献
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《传热工程》2012,33(9):775-785
A geometrically similar model of the proposed Advanced Heavy Water Reactor being designed and built by Bhabha Atomic Research Centre has been conceived and built at Indian Institute of Technology, Bombay. The basic objective of setting up such a facility and conducting experimental studies was to simulate the thermal-hydraulic behavior during the startup and also during part or full power operation. Owing to hydrodynamic instabilities observed in natural circulation system, it is necessary to know the stability boundaries. In this paper, the details of the experimental facility, experimental studies, and numerical simulations carried out using RELAP5/MOD 3.2 are discussed. Type I and type II stability boundaries and stable two-phase operation zones have been experimentally obtained at various pressures and inlet subcooling and the results are correlated using appropriate nondimensional numbers. Further, the experimental facility is modeled using the thermal-hydraulic code RELAP5/MOD 3.2. The single-phase pressure drops measured in the loop are used to estimate the appropriate loss coefficients used in the model. The model is then used to predict stability boundaries, and the predictions are compared with the experimental findings. The details of the experimental model and simulation results are presented. The capability of RELAP5/MOD 3.2 to predict the flow oscillations during instabilities is discussed. 相似文献
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The wide range of applications of two-phase natural circulation loops (NCLs) demands intense analyses of boiling systems, and consequently a large number of experimental and theoretical research findings are available in the literature. This comprehensive review focuses on the state-of-the-art appraisal of the related technology, with a primary focus on studies carried out in the last two decades. General modeling strategies have been reported and compared. Different forms of thermal-hydraulic instabilities appearing in two-phase NCLs have been summarized, with discussions on possible ways of identification and their differences. In addition, studies on system instability are presented in a categorywise grouping following a chronological style in terms development of knowledge. Coupled nuclear instabilities are reported as well in some detail. Finally, this review identifies the gray areas where the information is not quite complete and suggests the required path of future research. 相似文献
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Boiling experiments were performed on new, chemically cleaned, and fouled steam generator tubes to determine the heat transfer performance of each. It was found that the heat transfer performance of the fouled tube was the best, followed by the chemically cleaned tube. The performance of the new tube was the worst. Scanning electron microscope (SEM) photographs of the boiling surfaces were taken to identify differences in surface characteristics. Results revealed the presence of significant amounts of porous deposits on the surface of the fouled tube that provided ample nucleation sites for boiling. Chemical cleaning removed most of the deposits such that the boiling performance of the cleaned surface was degraded. The new tube was very smooth and there were relatively fewer nucleation sites as evidenced in the SEM photographs. Available correlations were used to predict the heat flux for a given wall superheat and were compared with the experimental data. 相似文献
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根据热量平衡原理,提出了一种简单直观的计算分析计算方法对锅炉启动过程中的过热器超温的原因进行了分析和化证。其结论与实际的测量结果一致。该结论揭示了锅炉启动过程中过热器超温的实质,对过热器超温机理的研究和提出解决过热器超温的措施有一定的参考价值。 相似文献
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根据实际运行数据研究了超超临界锅炉的汽温偏差变化规律和影响汽温偏差的特殊因素。指出特殊因素为:在湿态向干态转变和跨越临界点时工质热物理特性变化大;过热器系统的蒸汽流程延长、汽温偏差的累积效应增大;水煤比变化等;必须注意单侧减温水量过大,将加剧流量偏差,甚至引发临界流,进而扩大汽温偏差。实例反映的汽温偏差变化趋势为:超临界锅炉在低负荷运行阶段汽温偏差最大;在临界压力附近,汽温偏差被放大;在90%负荷以上过热器出口汽温偏差可以控制在低于5℃的设计值。对于制造、安装和焊接等工艺质量引起的超温爆管或流量偏差更要高度重视。 相似文献