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首页> 外文期刊>Nuclear engineering and technology >Development of a computer code for thermal–hydraulic design and analysis of helically coiled tube once-through steam generator
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Development of a computer code for thermal–hydraulic design and analysis of helically coiled tube once-through steam generator

机译:开发用于热工水力设计和螺旋线圈​​直通蒸汽发生器分析的计算机代码

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摘要

The Helically coiled tube Once-Through Steam Generator (H-OTSG) is a key piece of equipment for compact small reactors. The present study developed and verified a thermal–hydraulic design and performance analysis computer code for a countercurrent H-OTSG installed in a small pressurized water reactor. The H-OTSG is represented by one characteristic tube in the model. The secondary side of the H-OTSG is divided into single-phase liquid region, nucleate boiling region, postdryout region, and single-phase vapor region. Different heat transfer correlations and pressure drop correlations are reviewed and applied. To benchmark the developed physical models and the computer code, H-OTSGs developed in Marine Reactor X and System-integrated Modular Advanced ReacTor are simulated by the code, and the results are compared with the design data. The overall characteristics of heat transfer area, temperature distributions, and pressure drops calculated by the code showed general agreement with the published data. The thermal–hydraulic characteristics of a typical countercurrent H-OTSG are analyzed. It is demonstrated that the code can be utilized for design and performance analysis of an H-OTSG.
机译:螺旋盘管直流蒸汽发生器(H-OTSG)是紧凑型小型反应堆的关键设备。本研究开发并验证了安装在小型压水堆中的逆流H-OTSG的热工设计和性能分析计算机代码。 H-OTSG由模型中的一根特征管表示。 H-OTSG的次级侧分为单相液体区,成核沸腾区,干后区和单相蒸气区。审查并应用了不同的传热相关性和压降相关性。为了对开发的物理模型和计算机代码进行基准测试,通过代码对在Marine Reactor X和系统集成的模块化高级ReacTor中开发的H-OTSG进行了仿真,并将结果与​​设计数据进行了比较。通过该代码计算出的传热面积,温度分布和压降的总体特征与已发布的数据基本一致。分析了典型逆流H-OTSG的热工水力特性。证明了该代码可用于H-OTSG的设计和性能分析。

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