首页> 外文会议>International meeting on severe accident assessment and management 2012: Lessons learned from fukushima dai-ichi >APPLICABILITY AND EFFECTS ON SAFETY IMPROVEMENT OF CONTAINMENT FILTERED VENT SYSTEM IN OPR1000
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APPLICABILITY AND EFFECTS ON SAFETY IMPROVEMENT OF CONTAINMENT FILTERED VENT SYSTEM IN OPR1000

机译:OPR1000中安全壳过滤通风系统的安全改进的适用性和效果

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摘要

After the Fukushima Dai-ichi nuclear power plant accident, the Korean government and nuclear industries performed comprehensive special safety inspections on all domestic nuclear power plants against beyond design bases external events. As a result, a total of 50 recommendations were defined as safety improvement action items. One of the major action items is installation of a containment filtered vent system or temporary backup containment spray system. In this paper, the applicability and effects on safety improvement of containment filtered vent system (CFVS) in OPR1000, 1000MWth PWR in Korea, are examined. Thermo-hydraulic analysis results show that a filtered discharge flow rate of 6 [kg/s] is sufficient to depressurize the containment against major severe accident scenarios. When containment pressure reaches CFVS operating set-point at approximately 11 hours after the initiating events, CFVS effectively depressurizes the containment and maintains its integrity. In addition, the probability of maintaining the containment integrity in level 2 Probabilistic Safety Assessment (PSA) initiating events is improved two-fold, from 43% to 86%. The CFVS can thus further improve the safety of containment integrity in OPR1000 with respect to the severe accident mitigation strategy and PSA. As a further study item, adverse effects, such as containment negative pressure and local hydrogen concentration buildup, should be examined to guarantee the overall safety improvement effects of the CFVS.
机译:福岛第一核电站事故发生后,韩国政府和核工业针对超出设计基准的外部事件对所有国内核电站进行了全面的特殊安全检查。结果,总共定义了50条建议作为安全改进措施项目。主要措施之一是安装密闭过滤排气系统或临时备用密闭喷雾系统。本文研究了韩国1000MWth压水堆OPR1000中密闭过滤通风系统(CFVS)的适用性及其对安全性改进的影响。热工水力分析结果表明,过滤后的排放流量为6 [kg / s]足以使安全壳在重大的严重事故情况下减压。当安全壳压力在启动事件后约11小时达到CFVS操作设定点时,CFVS有效地降低安全壳的压力并保持其完整性。此外,在2级概率安全评估(PSA)启动事件中保持密闭完整性的可能性从43%提高到了86%,提高了两倍。因此,就严重事故缓解策略和PSA而言,CFVS可以进一步提高OPR1000中安全壳完整性的安全性。作为进一步的研究项目,应检查负面影响,例如安全壳负压和局部氢浓度的升高,以确保CFVS的整体安全性得到改善。

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  • 会议地点 San Diego CA(US)
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    Central Research Institute of Korea Hydro Nuclear Power Co., Ltd 70, 1312-gil, Yuseong-Daero, Yuseong-Gu, Daejeon, 305-343, Korea;

    Central Research Institute of Korea Hydro Nuclear Power Co., Ltd 70, 1312-gil, Yuseong-Daero, Yuseong-Gu, Daejeon, 305-343, Korea;

    Central Research Institute of Korea Hydro Nuclear Power Co., Ltd 70, 1312-gil, Yuseong-Daero, Yuseong-Gu, Daejeon, 305-343, Korea;

    Central Research Institute of Korea Hydro Nuclear Power Co., Ltd 70, 1312-gil, Yuseong-Daero, Yuseong-Gu, Daejeon, 305-343, Korea;

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