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Effectiveness of the raw-water system as a severe-accident-management measure in station blackout accidents

机译:原水系统作为车站停电事故中严重事故管理措施的有效性

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摘要

Chinshan is a Mark-I boiling water reactor nuclear power plant (NPP) located in north Taiwan. It incorporates several severe-accident-mitigating features, especially two raw-water tanks in the mountain. According to a probabilistic risk assessment (PRA) of Chinshan NPP, station blackout (SBO) sequences are the most dominant sequences in internal core damage frequency. No credit is taken for the raw-water system in the development of a Chinshan PRA. Therefore, two dominant sequences (T3UTERDGX and T3UTERDG) of the SBO in the Chinshan PRA are cited as reference cases to evaluate the capacity of the raw-water system in the PRA and severe accident. The T3UTERDGX sequence is initiated by loss of off-site power (T-3) followed by failure of both diesel generators (D-G), failure of gas turbine generators, and failure to recover alternating current (ac) power (E-R). That results in loss of all on- and off-site ac power. The high-pressure injection systems fail (UT) initially and timely reactor depressurization fails (X). The T3UTERDG sequence is the same as the T3UTERDGX sequence, except for failure of timely reactor depressurization (X). The MAAP4 code is used as a tool to evaluate the effectiveness of the raw-water system. Based on MAAP4 analysis, the raw-water system cannot cool down the core in the T3UTERDG sequence after introducing severe-accident-management guidelines. The raw-water system cannot flood dry-well water level above minimum debris submerge level (MDSL) in the T3UTERDGX sequence after reactor pressure vessel (RPV) breach. Sensitivity studies show that raw-water injection before the vessel water level reaches level 2 (L-2) can keep core coolability in the T3UTERDG sequence. Three times the raw-water injection rate is the minimum flow rate to flood the dry-well water level above MDSL and cool down the corium on the dry-well floor in the T3UTERDGX sequence. A raw-water system can be. used as a mitigating measure, especially in an SBO. The RPV should be depressurized as quickly as possible if a raw-water system is the only mitigation measure in the accident. It is worthwhile to increase the raw-water flow rate to cool down the debris in the dry well after RPV breach.
机译:金山是位于台湾北部的Mark-I沸水堆核电站。它具有减轻严重事故的功能,特别是在山上的两个原水箱中。根据金山核电厂的概率风险评估(PRA),停电(SBO)序列是内部核心损坏频率中最主要的序列。在金山PRA的开发中,对原水系统不容置疑。因此,引用金山PRA中SBO的两个主要序列(T3UTERDGX和T3UTERDG)作为参考案例,以评估PRA中的原水系统的容量和严重事故。 T3UTERDGX序列由场外电源(T-3)丢失,两台柴油发电机(D-G)发生故障,燃气轮机发电机发生故障以及交流电(ac)功率恢复失败(E-R)引发。这将导致所有现场和场外交流电源的损耗。高压喷射系统最初会失效(UT),而反应堆及时降压会失效(X)。 T3UTERDG序列与T3UTERDGX序列相同,除了无法及时对反应堆减压(X)。 MAAP4代码用作评估原水系统有效性的工具。根据MAAP4分析,在引入严重事故管理指南后,原水系统无法冷却T3UTERDG序列中的岩心。反应堆压力容器(RPV)破裂后,原水系统无法将T3UTERDGX序列中的干井水位淹没到最低碎片淹没水位(MDSL)以上。敏感性研究表明,在容器水位达到2级(L-2)之前注入原水可以保持T3UTERDG序列中的岩心可冷却性。原水注入速率的三倍是最小流量,它使T3UTERDGX序列中的干井水位充满MDSL并冷却干井底板上的皮质。可以是原水系统。用作缓解措施,尤其是在SBO中。如果原水系统是事故中唯一的缓解措施,则应尽快给RPV降压。 RPV突破后,增加原水流速以冷却干井中的碎屑是值得的。

著录项

  • 来源
    《Nuclear Technology》 |2006年第3期|p. 347-359|共13页
  • 作者

    Wang TC; Wang SJ; Teng JT;

  • 作者单位

    Chung Yuan Christian Univ, Chungli 32023, Taiwan;

    Inst Nucl Energy Res, Jiaan Village 32546, Taoyuan County, Taiwan;

  • 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 原子能技术;
  • 关键词

    BWR; raw water; MAAP;

    机译:BWR;原水;MAAP;

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