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The nuclear industry has made so great efforts to attain safe and economically viable Nuclear Power Plants all over the world. Probabilistic Safety Assessment (PSA) applications are required now more than ever in order to operate Nuclear Power Plants.In this paper, the unavailability model of Engineered Safety Feature (ESF) actuated components, which is part of the Korean Standard Nuclear Power Plant (KSNPP) PSA model, is used to analyze the effects of Surveillance Test Interval (STI) extension of Engineered Safety Feature Actuation System (ESFAS) on the unavailability of the ESF actuated components.To develop a more accurate and realistic PSA model, the loop controller modules of Plant Control System (PCS) are also modeled on the KSNPP PSA model. The fault tree developed by each ESF actuated component includes the component failure, ESFAS signal failure, and loop controller module failure of PCS. When the ESFAS STI is extended from one month to three months, the unavailability of ESF actuated components partially increased by 10%. This shows the STI extension of ESFAS has minor effects on the unavailability of the ESF actuated components. The effects of ESFAS STI extension of KSNPP on the unavailability of the ESF actuated components as well as Core Damage Frequency (CDF) and Large Early Release Frequency (LERF) is less than expected. That result indirectly indicates that the ESFAS in KSNPP is designed well enough to extend the ESFAS STI. 相似文献
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针对核电厂防火设计中使用的火灾区域模型模拟软件CFAST(Consolidated Model of Fire Growth and Smoke Transport)在火源模型方面的缺陷,提出耦合火源与热烟气层的热反馈相互作用的火源计算模型。为了验证新的火源功率计算模型的可靠性,基于核电厂保守性原则,分别进行了开放空间和封闭空间内横向四层电缆桥架电缆燃烧火灾实验。通过比较模型预测的火源功率和温度与实验测量值得到:相对于现有的区域模型软件的火源计算模型,新的火源功率计算模型使得整个火灾过程中火源的热释放速率预测精确度提高了11%;特别是在电缆火焰横向蔓延阶段,精确度提高了24.7%。更重要的是:因为区域模型软件CFAST火源计算模型忽略了烟气的热反馈作用,导致其基于开放空间火源热释放速率测量值计算的热烟气层温度小于实验测量值,该温度数据如用于防火设计将导致缺乏保守性;而修正后的火源计算模型通过耦合火源与热烟气层热反馈的相互作用,使得温度计算结果趋势性的大于实验测量值,使得预测结果趋于精确和保守。 相似文献
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田湾核电站工程概况和安全设计特点 总被引:1,自引:0,他引:1
简介田湾核电站的中俄合作建设模式和工作进展概况,叙述改进型俄式百万千瓦级压水堆核电机组(简称WWER-1000/AES-91型核电机组)的安全设计特点。其中包括反应堆堆芯、主回路、安全系统以及棒它工程安全设施等方面的改进,特别是减轻超设计基准事故后果的改进措施。 相似文献
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核电站物项的安全分级工作中应特别注意全局性、适度性、均衡性这3项原则.物项安全分级的;基本方法,一般是根据物项(部件)的承压外壳损坏对安全的影响,对物项的安全功能进行分级田湾核电站采用的是俄罗斯VVER-1000/428型反应堆装置,其物项安全分级主要采用俄罗斯法规标准:电气和仪控设备采用IEEE-308(80)标准,分为1E级与非1E级;仪控系统及设备的安全分级采用国内标准GB/T15474—1995,分为安全1E级,安全相关SR级和NC非安全级,田湾核电站物项的安全分级必须经中国核安全当局审批并满足中国核安全法规要求. 相似文献
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本文主要介绍概率安全评价中的事故后果评价方法学以及与此相关的内容,如ACA输入的源项、模式参数对后果的影响,评价ACA结果的概率安全准则;同时结合广东大亚湾核电站PSA中的后果和风险分析,说明ACA中模式和参数的使用。文中还列举说明了ACA在应急计划中的应用。 相似文献
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In Probabilistic Safety Assessment (PSA) all attention is paid to analyze a system which is a time consuming effort so there is a need to develop a system network to support the analyst and to reduce manpower. To handle the physical, operational and organizational changes and to utilize the PSA information effectively the development of living Probabilistic Safety Assessment (LPSA) is essential. This paper presents a detailed methodology for LPSA. One part of this methodology is Advanced Control Room Operator Support System (ACROSS) which is helpful for updating the LPSA model. This methodology also provides help to make the control rooms in Nuclear Power Plants (NPPs) more advanced and user friendly. The study also makes recommendations for further use and development of this technique in the present and future NPPs. 相似文献
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以福建福清核电厂一期工程乏燃料水池为研究对象,对可能威胁乏燃料水池安全的内部始发事件进行了概率安全分析。评价了乏燃料水池中燃料元件损坏的风险,并将实施应急补水及液位连续监测这两项设计改进后的定量化结果与改进前的定量化结果进行比较分析。结果表明,改进项的实施明显降低了乏燃料水池燃料元件损坏的风险。 相似文献
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HFETR安全参数显示系统中安全参数的选择 总被引:1,自引:1,他引:0
根据HFETR(高通量工程试验堆)的安全分析报告,参照核电厂的安全法规,经过认真分析高通量工程试验堆在多年的运行中所发生的故障,事件和事故,将其安全功能划分为反应性控制,堆芯冷却,堆芯热导出,一回路压力边界完整性,放射性控制5个关键安全功能,根据这5个关键安全功能,选择了能够全在评估反应堆安全状态,代表高通量工程试验堆各安全功能的一组主特征参数。 相似文献
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当前法律和法规规定,对核电厂安全系统使用的核安全级数字设备必须对其硬件和软件进行鉴定。软件设计和编码是软件通过鉴定关键的一环。核安全级软件必须具备可确定性的特征,其设计和编码必须体现这一特征。对于核安全级软件设计和编码如何满足核安全要求的研究,是软件厂商和监管当局面临的问题之一。 相似文献
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结合三门和海阳核电厂厂用水系统的实际设计,考虑各运行工况下的运行要求,特别是系统布置相关性的影响,通过概率安全评价(PSA)建模确定了系统可用性情况及其相应的风险结果。基于风险分析的结果,为三门核电厂的设计缺陷提出了合理的改进建议方案,从而提高了该电厂的安全性和经济性。同时结合海阳核电厂的实际情况,分析结果认为基本无改进必要,充分体现了PSA对设计的支持和指导作用。 相似文献
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本文就高通量工程试验堆、岷江试验堆和中国脉冲堆特点作出比较,重点分析高通量工程试验堆的安全性。经过比较,中国脉冲具有良好的安全性,安全性远比岷江试验堆和高通量工程试验堆好;高通量工程试验堆由于建造时间早,功率规模大,风险程度比岷江试验堆高。因此,必须加强高通量工程试验堆安全整治,才能确保该反应堆运行安全。 相似文献
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This paper presents the results received during investigation of hydrogen generation for both types fuel assemblies—the old modernistic type of fuel assemblies (TVSM) and recently installed new one alternative type of fuel assemblies (TVSA) in case of severe accident. There are some differences between both types FAs. They have different geometry as well as different burnable poisons. To investigate behavior of new fuel assemblies during the severe conditions it have been performed comparison of fuel behavior of old type TVSM fuel assembly to new one TVSA.To perform this investigation it has been used MELCOR “input model” for Kozloduy Nuclear Power Plant (KNPP) VVER 1000. The model was developed by Institute for Nuclear Research and Nuclear Energy-Bulgarian Academy of Sciences (INRNE-BAS) for investigation of severe accident scenarios and Probabilistic Safety Analyses (PSA) level 2. The model provides a significant analytical capability for the Bulgarian technical specialists, working in the field of the NPP safety, for analysis of core and containment damaged states and the estimation of radionuclides release outside fuel cladding.It was accepted criteria for vessel integrity about hydrogen concentration to be 8%. This criterion was based on the decision of RSK (Germany commission for reactor safety).Generally based on the received results it was made conclusion that using both types of fuel assemblies it was not disturbance safety conditions of NPP. 相似文献
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人的可靠性分析是广东核电站PSA研究中的一个重要部分,其目的是研究电站中人的行为对反应堆堆芯熔化频率的影响,文章对广东核电站事故序列中可能出现的人误进行了定性和定量化分析,给出了PSA研究中需要的人误概率值。详细的人因分析将在以后的工作中进行。 相似文献
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