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Detailed evaluation of safety injection tank effects on in-vessel severe accident progression in a small break LOCA without safety injection

机译:在没有安全注入的小间隔LOCA中,安全注入罐对船上严重事故进展的影响的详细评估

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摘要

The effects of coolant injection into a reactor vessel by the passive actuation of SITs (Safety Injection Tanks) on the in-vessel core melt progression under a severe accident have been evaluated in an APR (Advanced Power Reactor) 1400. A best estimate simulation from initiating events of 2-in. and 3-in. break SBLOCAs (Small Break Loss Coolant Accidents) without SI (Safety Injection) to a reactor vessel failure has been carried out using the SCDAP/RELAP5 computer code in conditions with and without the passive actuation of the SITs. The SCDAP/RELAP5 results have shown that the passive coolant injection into the reactor vessel by the actuation of the SITs leads to postpone the reactor vessel failure time by 4-5 h in the SBLOCA without SI. At the time of the reactor vessel failure, 44.5% and 42.8% of the fuel rod cladding were oxidized in the 2-in. and 3-in. SBLOCAs with the actuation of the SITs, respectively. However, 37.5% and 34.6% of the fuel rod cladding were oxidized in the 2-in. and the 3-in. SBLOCAs without the actuation of the SITs, respectively. Even though the SITs are designed for a large break LOCA, their actuation is very effective on the delay of a reactor vessel failure in spite of more hydrogen generation in the SBLOCA without SI.
机译:在APR(先进动力堆)1400中,评估了严重事故下通过SIT(安全注入箱)的被动致动将冷却剂注入反应堆容器对堆芯内融化进程的影响。 2英寸启动事件。和3英寸使用SCDAP / RELAP5计算机代码在无SIT被动驱动的情况下,将没有SI(安全注入)的SBLOCA(小断裂损失冷却液事故)破坏到反应堆容器故障。 SCDAP / RELAP5结果表明,在没有SI的情况下,通过SIT的驱动将被动冷却剂注入反应堆容器会导致反应堆容器故障时间推迟4-5小时。在反应堆容器发生故障时,在2英寸中,有44.5%和42.8%的燃料棒包壳被氧化。和3英寸SBLOCA与SIT分别致动。但是,在2英寸中有37.5%和34.6%的燃料棒包壳被氧化。和三合一不带SIT的SBLOCA。即使将SIT设计用于大破坏LOCA,尽管在没有SI的SBLOCA中产生了更多的氢气,但它们的启动对于反应堆容器故障的延迟非常有效。

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  • 来源
    《Annals of nuclear energy》 |2013年第8期|54-59|共6页
  • 作者单位

    Severe Accident and PHWR Safety Research Division, Korea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-gu, Daejeon 305-353, Republic of Korea;

    Severe Accident and PHWR Safety Research Division, Korea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-gu, Daejeon 305-353, Republic of Korea;

    Severe Accident and PHWR Safety Research Division, Korea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-gu, Daejeon 305-353, Republic of Korea;

    Severe Accident and PHWR Safety Research Division, Korea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-gu, Daejeon 305-353, Republic of Korea;

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

    Severe accident; Actuation of safety injection tanks; Passive coolant injection; Core melt progression; Hydrogen generation; Reactor vessel failure;

    机译:严重事故;启动安全注入箱;被动冷却液注入;核心融化进展;氢气产生;反应堆容器故障;

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