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Preliminary design of the I~2S-LWR containment system

机译:I〜2S-LWR遏制系统的初步设计

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摘要

The Integral Inherently Safe Light Water Reactor ((IS)-S-2-LWR) is a novel reactor design concept which aims at delivering an electric power output level comparable to that of large LWRs (approximately 1000 MWe), while at the same time achieving an overall level of safety that is enhanced with respect to large Generation III+ LWRs. One of the main safety goals is to achieve indefinite cooling following design basis accidents (DBAs) using atmosphere air as ultimate heat sink. In order to accommodate these goals, the (IS)-S-2-LWR incorporates several innovative safety features, including an integral Reactor Pressure Vessel (RPV), enhanced passive Decay Heat Removal (DHR) systems and several containment passive cooling systems. The present work is focused on a passive and reliable containment design, which plays a significant role in LOCA scenario and is the last boundary to prevent the release of radioactivity to the environment. In this paper, several innovative passive systems located in the (IS)-S-2-LWR containment are proposed, including Core Make-up Tank (CMT), Accumulator (ACC), Passive Suppression System (PSS), Automatic Depressurization System (ADS), Passive Containment Cooling System (PCCS) and Passive Reactor Cavity Cooling System (PRCCS). The best-estimate thermal-hydraulic code RELAP5 has been used to model the (IS)-S-2-LWR RPV and containment passive systems. The inadvertent opening of PORV (Power Operated Relief Valve) accident scenario has been simulated in order to study the containment response, including the coupling between RPV and containment. The results show that, through the activation of the ADS, pressure equilibrium between containment and reactor pressure vessel is achieved, while maintaining the reactor core covered at all times. The containment passive cooling systems ensure that the containment pressure remains at acceptable levels throughout the transient. A sensitivity study on the number of operating ADS valves, and on the availability of accumulators is also performed. (C) 2018 Published by Elsevier Ltd.
机译:整体固有安全的轻水反应器((是)-S-2-LWR)是一种新型反应堆设计理念,其旨在提供与大型LWR(约1000米)相当的电力输出水平,同时实现关于大一代III + LWR的总体安全水平。主要的安全目标之一是使用大气空气作为最终散热器实现设计基础事故(DBA)的无限冷却。为了适应这些目标,(IS)-S-2-LWR包含多种创新的安全功能,包括整体反应堆压力容器(RPV),增强的被动衰变除去(DHR)系统和多个容纳被动冷却系统。本工作专注于被动且可靠的遏制设计,它在基因座情景中起着重要作用,并且是防止对环境释放放射性的最后边界。在本文中,提出了几种位于(是)-S-2-LWR遏制的创新无源系统,包括核心化妆罐(CMT),蓄能器(ACC),被动抑制系统(PSS),自动减压系统(广告),被动遏制冷却系统(PCCS)和无源反应器腔冷却系统(PCCS)。最佳估计的热液压代码RELAP5已用于模拟(IS)-S-2-LWR RPV和容纳被动系统。已经模拟了PORV(动力释放阀)事故情景的无意开口,以研究容纳响应,包括RPV和遏制之间的耦合。结果表明,通过ADS的激活,实现了容纳和反应器压力容器之间的压力平衡,同时保持始终覆盖的反应器芯。遏制被动冷却系统确保容纳压力在整个瞬态的可接受水平处保持在可接受的水平。还执行了对操作广告阀数量的敏感性研究以及累加器的可用性。 (c)2018年由elestvier有限公司发布

著录项

  • 来源
    《Annals of nuclear energy》 |2020年第9期|106065.1-106065.11|共11页
  • 作者单位

    Xi An Jiao Tong Univ Dept Nucl Sci & Technol Xian 710049 Peoples R China|Univ Michigan Dept Nucl Engn & Radiol Sci Ann Arbor MI 48109 USA;

    Univ Michigan Dept Nucl Engn & Radiol Sci Ann Arbor MI 48109 USA;

    Brigham Young Univ Dept Chem Engn Provo UT 84602 USA;

    Univ Michigan Dept Nucl Engn & Radiol Sci Ann Arbor MI 48109 USA;

    Xi An Jiao Tong Univ Dept Nucl Sci & Technol Xian 710049 Peoples R China;

    Xi An Jiao Tong Univ Dept Nucl Sci & Technol Xian 710049 Peoples R China;

    Xi An Jiao Tong Univ Dept Nucl Sci & Technol Xian 710049 Peoples R China;

  • 收录信息
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    Inherent integral reactor; Containment; SBLOCA; Passive cooling system;

    机译:固有的整体反应堆;遏制;SBLOCA;被动冷却系统;

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