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Comparison of Two Different Sized Small-Break LOCAs on the Passive Safety Injection Line Using SMART-ITL Data

机译:使用SMART-ITL数据比较两种不同大小的小型垫盘上的无源安全注入线路

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Even for small modular reactors (SMRs) with all large pipes removed, a small-break loss-of-coolant accident (SBLOCA) is an important design-basis accident (DBA). Experimental simulation of the SBLOCA scenario is essential before a prototype reactor is realized. The system-integrated modular advanced reactor (SMART) is one of the SMRs developed by the Korea Atomic Energy Research Institute. An integral test loop, SMART-ITL, was also constructed to carry out several types of integral thermal-hydraulic effects tests for the prototype reactor. The SMART-ITL was designed with a preserved height, I/7th diameter, and 1749th area, and volume-scaling ratios. Two types of passive safety systems were equipped in the SMART-ITL: a passive safety injection system (PSIS) and a passive residual heat removal system (PRHRS). The PSIS was designed to refdl the coolant in the reactor coolant system (RCS)for 72 h after an accident. Under accident conditions the PRHRS prevents overheating and overpressurization of the RCS using two-phase natural circulation. The SBLOCA on the passive safety injection line is a significant DBA that should be validated for differences in break size. In this paper, the effects of two different break sizes, 2 and 7/32 in., were analyzed in order to study the effect of the maximum and minimum mass and energy loss of the RCS. In order to simulate a clear difference between maximum and minimum mass and energy loss of the RCS, heat removal by the PRHRS was performed in the maximum break size (2-in.) accident, and heat removal by the PRHRS was not conducted in the minimum break size (7/32-in.) accident. The difference in mass and energy loss of the RCS will have a significant impact on the operation of the automatic depressurization system. Using the two extreme accident simulations, it was possible to confirm the difference in accident progression caused by the difference in break size and the characteristics of the PSIS.
机译:即使对于小型模块化反应器(SMRS),除了所有大型管道,均匀的冷却液丧失事故(SBLOKA)是一个重要的设计基础事故(DBA)。在实现原型反应器之前,SBLOCA情景的实验模拟是必需的。系统集成的模块化高级反应堆(SMART)是韩国原子能研究所开发的SMR之一。还构造了一个积分测试回路,Smart-ITL,用于对原型反应器进行几种类型的积分热液压效应试验。 SMART-ITL设计具有保存的高度,I / 7th直径和1744个区域,以及缩放比率。在Smart-ITL中配备了两种类型的无源安全系统:被动安全注入系统(PSI)和被动残留的散热系统(PRHRS)。贴上诗歌被设计为在事故发生后的反应器冷却剂系统(RCS)中的冷却剂。在意外条件下,使用两相自然循环,PRHRS防止RCS过热和过度升压。被动安全注入线上的SBLOCA是一个重要的DBA,应该验证折断尺寸的差异。在本文中,分析了两种不同断裂尺寸,2和7/32的影响,以研究最大和最小质量和rcs的能量损失的影响。为了模拟RCS的最大和最小质量和能量损失之间的明显差异,PRHRS的热除去在最大断裂尺寸(2-IN)事故中进行,并且在PRHR的热量除外最小断裂尺寸(7/32英寸)事故。 RCS的质量和能量损失的差异对自动减压系统的操作产生了重大影响。使用两个极端的事故模拟,可以确认由断裂尺寸的差异和PSI的特征引起的事故进展的差异。

著录项

  • 来源
    《Nuclear Technology》 |2020年第9期|1421-1435|共15页
  • 作者单位

    Korea Atomic Energy Research Institute Innovative System Safety Research Division 989-111 Daedeokdaero Yuseong Daejeon 34057 Republic of Korea;

    Korea Atomic Energy Research Institute Innovative System Safety Research Division 989-111 Daedeokdaero Yuseong Daejeon 34057 Republic of Korea;

    Korea Atomic Energy Research Institute Innovative System Safety Research Division 989-111 Daedeokdaero Yuseong Daejeon 34057 Republic of Korea;

    Korea Atomic Energy Research Institute Innovative System Safety Research Division 989-111 Daedeokdaero Yuseong Daejeon 34057 Republic of Korea;

    Korea Atomic Energy Research Institute Innovative System Safety Research Division 989-111 Daedeokdaero Yuseong Daejeon 34057 Republic of Korea;

    Korea Atomic Energy Research Institute Innovative System Safety Research Division 989-111 Daedeokdaero Yuseong Daejeon 34057 Republic of Korea University of Science and Technology Advanced Nuclear System Engineering 217 Gajeong-ro Yuseong-gu Daejeon 34113 Republic of Korea;

  • 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);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    SMART; SMART-ITL; small-break loss-of-coolant accident; passive safety injection system; automatic depressurization system;

    机译:聪明的;智能ITL;小休息丧失冷却液事故;被动安全注射系统;自动减压系统;

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