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Design and transient analyses of emergency passive residual heat removal system of CPR1000

机译:CPR1000应急被动余热排除系统的设计与暂态分析

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摘要

The steam generator secondary emergency passive residual heat removal system (EPRHRs) is a new design for traditional generation Ⅱ + reactor CPR1000. The EPRHRs is designed to improve the safety and reliability of CPR1000 by completely or partially replacing traditional emergency water cooling system in the event of the station blackout or loss of heat sink accident. The EPRHRs consists of steam generator (SG), heat exchanger (HX), emergency makeup tank (EMT), cooling water tank (CWT), and corresponding pipes and valves. In order to improve the safety and reliability of CPR1000, the model of the primary loop and the EPRHRs was developed to investigate residual heat removal capability of the EPRHRs and the transient characteristics of the primary loop affected by the EPRHRs using RELAP5/MOD3.4. The transient characteristics of the primary loop and the EPRHRs were calculated in the event of station blackout accident. Sensitivity studies of the EPRHRs were also conducted to investigate the response of the primary loop and the EPRHRs on the main parameters of the EPRHRs. The EPRHRs could supply water to the SG shell side from the EMT successfully. The calculation results showed that the EPRHRs could take away the decay heat from the primary loop effectively, and that the single-phase and two-phase natural circulations were established in the primary loop and EPRHRs loop, respectively. The results also indicated that the effect of isolation valve open time on the transient characteristics of the primary loop was little. However, the effect of isolation valve open time on the EPRHRs condensate flow was relatively greater. The isolation valves should not be opened too rapidly during the isolation valve opening process, and the isolation valve opening time should be greater than 10 s, which could avoid the steam impact on the EPRHRs, and improve the stability of the system.
机译:蒸汽发生器二次应急被动余热去除系统(EPRHRs)是传统Ⅱ+反应堆CPR1000的一种新型设计。 EPRHRs旨在通过在站点停电或发生散热片事故时完全或部分替换传统的应急水冷却系统来提高CPR1000的安全性和可靠性。 EPRHR由蒸汽发生器(SG),热交换器(HX),应急补给箱(EMT),冷却水箱(CWT)以及相应的管道和阀门组成。为了提高CPR1000的安全性和可靠性,开发了主回路和EPRHRs的模型,以研究RELAP5 / MOD3.4的EPRHRs的残余排热能力以及受EPRHRs影响的主回路的瞬态特性。在发生车站停电事故的情况下,计算了主回路和EPHRR的瞬态特性。还进行了EPRHRs的敏感性研究,以调查主循环和EPRHRs对EPRHRs主要参数的响应。 EPRHR可以成功地从EMT向SG壳侧供水。计算结果表明,EPHRRs可以有效地消除一次回路的衰变热,并且在一次回路和EPHRRs回路中分别建立了单相和两相自然循环。结果还表明,隔离阀打开时间对一次回路的瞬态特性的影响很小。但是,隔离阀打开时间对EPRHRs冷凝水流量的影响相对较大。在隔离阀开启过程中,隔离阀的开启时间不能太快,隔离阀的开启时间应大于10 s,这样可以避免蒸汽对EPRHR的影响,并提高系统的稳定性。

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  • 来源
    《Nuclear Engineering and Design》 |2012年第1期|p.247-256|共10页
  • 作者单位

    Department of Nuclear Science and Technology, Xi'art Jiaotong University, Xi'an City 710049, China;

    Department of Nuclear Science and Technology, Xi'art Jiaotong University, Xi'an City 710049, China;

    Department of Nuclear Science and Technology, Xi'art Jiaotong University, Xi'an City 710049, China;

    Department of Nuclear Science and Technology, Xi'art Jiaotong University, Xi'an City 710049, China;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
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  • 正文语种 eng
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