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SEVERE EXTERNAL HAZARD ON HYPOTHETICAL JSFR IN 2010

机译:2010年假想JSFR的严重外部危害

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摘要

Severe external hazards on the Japan Sodium-cooled Fast Reactor (JSFR) have been analyzed and evaluated. For seismic design, safety components are confirmed to maintain their functions even against recent strong earthquakes. Integrity of the major components has been confirmed covering recent earthquake conditions. In the case of a tsunami, the seawater pumps for the component cooling water system (CCWS) could be damaged by the tsunami, since they are located at sea level. In the JSFR design with full natural convection decay heat removal systems (DHRSs) and an air-cooling emergency gas turbine, safety-grade components are independent of CCWS, and loss of CCWS does not affect reactor cooling. As a conservative case, hypothetical station blackout (SBO) has been evaluated. In the case ofSBO, decay heat is removed by natural convection DHRS, but control of the air cooler (AC) damper is lost after the battery power is out. The analysis has revealed that freezing at one of three ACs could happen due to loss of automatic control of AC dampers. However, the time margin to protected loss of heat sink is evaluated to be >10 days. Manual control of the AC damper is also investigated. Transient analyses show that the AC dampers can be controlled manually adopting a simple operation procedure with sufficient operation time. Decay heat cooling in the case of collapse in all air stacks of AC has been evaluated. The result shows that decay heat could be removed maintaining air paths in two of three ACs by accident management. In conclusion, JSFR in the 2010 design version has enough external hazard toughness mainly thanks to passive safety features and a seismic isolation system.
机译:对日本钠冷快堆(JSFR)的严重外部危害进行了分析和评估。对于抗震设计,安全组件即使在最近的强烈地震中也能保持其功能。已经证实主要成分的完整性涵盖了最近的地震情况。在海啸的情况下,用于组件冷却水系统(CCWS)的海水泵可能会被海啸损坏,因为它们位于海平面上。在具有完全自然对流衰减除热系统(DHRS)和空冷应急燃气轮机的JSFR设计中,安全级组件独立于CCWS,并且CCWS的损失不会影响反应堆的冷却。作为保守的情况,已经评估了假设的车站停电(SBO)。对于SBO,通过自然对流DHRS消除了衰减的热量,但是在电池断电后,空气冷却器(AC)的风门失去了控制。分析显示,由于失去对AC风门的自动控制,可能会在三个AC之一发生冻结。但是,保护散热器损失的时间裕度估计为> 10天。还研究了交流风门的手动控制。瞬态分析表明,交流风门可以通过简单的操作步骤进行手动控制,并具有足够的操作时间。已经评估了AC的所有空气堆坍塌情况下的衰变热冷却。结果表明,通过事故管理,可以消除腐烂的热量,从而保持三个空调中的两个空调中的空气路径。总而言之,2010年设计版本的JSFR具有足够的外部危害韧性,这主要归功于被动安全功能和地震隔离系统。

著录项

  • 来源
    《Nuclear Technology》 |2015年第2期|111-124|共14页
  • 作者单位

    Vapan Atomic Energy Agency, 4002 Narita Oarai Higashi-ibaraki-gun, Ibaraki, Japan 311-1393;

    Vapan Atomic Energy Agency, 4002 Narita Oarai Higashi-ibaraki-gun, Ibaraki, Japan 311-1393;

    Vapan Atomic Energy Agency, 4002 Narita Oarai Higashi-ibaraki-gun, Ibaraki, Japan 311-1393;

    Mitsubishi FBR Systems Inc., Tokyo, Japan;

    Mitsubishi FBR Systems Inc., Tokyo, Japan;

  • 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

    sodium-cooled fast reactor; external hazard; station blackout;

    机译:钠冷快堆外部危害;车站停电;
  • 入库时间 2022-08-18 00:43:03

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