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Thermal hydraulics analysis of a helical coil steam generator of a small modular reactor

机译:小型模块化反应堆螺旋线圈蒸汽发生器的热力学分析

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In the present study, thermal hydraulic investigation of a steam generator of an integral small modular reactor (SMR) has been performed. For this investigation, a helical coil steam generator of IRIS design is selected due to availability of its design parameters in literature. Steam generator model is developed in RELAP5/Mod 4.0. At first, steady state simulation has been performed for this model and results are found in good agreement with the IRIS design data. In order to evaluate the behavior of steam generator under accidental conditions, transient analysis has also been performed. Steam generator performance is assessed for two transients, namely, feed line break (FLB) and loss of flow accident (LOFA). Exponential losses of secondary side pressures (inlet and outlet) are considered for FLB, whereas an exponential loss of primary flow rate is considered for LOFA. The results indicate safe and reliable operation of IRIS steam generator for both transients. (C) 2017 Elsevier Ltd. All rights reserved.
机译:在本研究中,对整体式小型模块化反应堆(SMR)的蒸汽发生器进行了热力水力研究。对于本研究,由于文献中提供了其设计参数,因此选择了IRIS设计的螺旋线圈蒸汽发生器。蒸汽发生器模型是在RELAP5 / Mod 4.0中开发的。首先,已经对该模型进行了稳态仿真,结果与IRIS设计数据非常吻合。为了评估意外条件下蒸汽发生器的性能,还进行了瞬态分析。蒸汽发生器的性能是针对两个瞬变进行评估的,即进料管线中断(FLB)和流失事故(LOFA)。对于FLB,考虑了二次侧压力(入口和出口)的指数损失,而对于LOFA,考虑了一次流量的指数损失。结果表明,IRIS蒸汽发生器在两种瞬态情况下均可安全可靠地运行。 (C)2017 Elsevier Ltd.保留所有权利。

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  • 来源
    《Annals of nuclear energy》 |2017年第11期|705-711|共7页
  • 作者单位

    PIEAS, Dept Nucl Engn, Ctr Studies Emerging Reactor Technol CERT, Islamabad, Pakistan;

    PIEAS, Dept Nucl Engn, Ctr Studies Emerging Reactor Technol CERT, Islamabad, Pakistan;

    PIEAS, Dept Nucl Engn, Ctr Studies Emerging Reactor Technol CERT, Islamabad, Pakistan;

    PIEAS, Dept Nucl Engn, Ctr Studies Emerging Reactor Technol CERT, Islamabad, Pakistan;

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