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首页> 外文期刊>Annals of nuclear energy >Development of thermal-hydraulic analysis code of a helically coiled once-through steam generator based on two-fluid model
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Development of thermal-hydraulic analysis code of a helically coiled once-through steam generator based on two-fluid model

机译：基于双流体模型的螺旋盘绕直流蒸汽发生器热工水力分析程序的开发

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A thermal-hydraulic analysis model, coupling the flow and heat transfer of the primary and secondary sides, is developed to describe the thermal hydraulic behavior of OTSG (helically coiled Once-Through Steam Generator). This numerical model is developed based on the two-fluid model with distributed parameters method to predict all flow variables at each position along the tube. Correlations, validated a lot, are adopted to consider the effect of helical structure on the flow and heat transfer of both the primary and secondary sides in OTSG. The computational code THOSG (Thermal-Hydraulic analysis code of Once-through Steam Generator) for OTSG is then developed based on the numerical model with the modified SIMPLE algorithm. To benchmark the developed physic model and computer code, steady-state simulation of OTSG of IRIS reactor is conducted. Results are compared with RELAP5 code with respect to the design parameters. Comparisons indicate that the THOSG code can predict the thermal-hydraulic characteristics of OTSG well. In order to investigate the effect of changes in the input conditions on the output of the OTSG, transient analysis has been performed. Simulations of change in feedwater flow rate and temperature are conducted to assess the performance of OTSG. Both steady-state and transient results indicate that the THOSG code can be utilized for the design and performance analysis of OTSG. However, further analysis, coupling with the thermal-hydraulic behavior of the reactor core, is required to comprehensively evaluate the safety and reliability of OTSG design in nuclear power plant. (C) 2019 Elsevier Ltd. All rights reserved.
机译：建立了一个热-水力分析模型，该模型耦合了一次侧和二次侧的流动和传热，以描述OTSG（螺旋盘绕一次通过式蒸汽发生器）的热力行为。该数值模型是基于具有分布参数方法的双流体模型开发的，以预测沿管的每个位置的所有流量变量。考虑到螺旋结构对OTSG初级侧和次级侧的流动和传热的影响，采用了经过大量验证的相关性。然后，使用改进的SIMPLE算法，基于数值模型，开发了用于OTSG的计算代码THOSG（直流蒸汽发生器的热工-液压分析代码）。为了对开发的物理模型和计算机代码进行基准测试，对IRIS反应堆的OTSG进行了稳态仿真。将结果与RELAP5代码的设计参数进行比较。比较表明，THOSG代码可以很好地预测OTSG的热工水力特性。为了研究输入条件变化对OTSG输出的影响，已进行了瞬态分析。进行给水流量和温度变化的模拟，以评估OTSG的性能。稳态和瞬态结果均表明THOSG代码可用于OTSG的设计和性能分析。但是，需要进行进一步分析，再加上反应堆堆芯的热工行为，以全面评估核电站OTSG设计的安全性和可靠性。 （C）2019 Elsevier Ltd.保留所有权利。

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