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Databases and their analysis for applications in quantitative risk analysis of NPP

机译:数据库及其分析在核电厂定量风险分析中的应用

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There are several equipment failure databases originating in the nuclear power plant that are successfully used in quantitative risk analysis applications Le, probabilistic safety assessment (PSA). Regulatory bodies (like AERB, India) now accept the importance and use of databases for safety and reliability studies in the nuclear industry as industry practice. Databases containing human error data originated from studies carried out in the nuclear industry and are used, in conjunction with equipment failure models to assess overall levels of safety to operation of a NPP. Based on these databases, very powerful risk analysis and reliability engineering methods such as Fault and Event tree methods are used to determine quantitatively what levels of safety, reliability and performance exist at one's plant operation and where improvement resources should be applied. Also, the use of risk informed approaches has been both identified and encouraged as an option to improve management of station resources more effectively and this technique has seen notable successes in the areas of in-service inspection and testing However, for any analysis a large database is required. Hence, compilation of data is key element and must for PSAto get the real picture and genuine results. This paper describes about the station practices that are followed at Rajasthan Atomic Power Station, Unit-3&4 regarding data collection from computerized maintenance management system (CMMS), which is a deficiency report based system in which deficiencies are raised and their subsequent follow up is done till their rectification. After reporting of a deficiency, work permits are applied by maintenance agency and these permits are subsequently issued by operation section and ultimately surrendered by maintenance agency after rectification of deficiency. Appropriate cause codes, failure codes and history of work being done is maintained in CMMS databases, which are referred to for their inclusion in P--SA model.
机译:有几个源自核电站的设备故障数据库已成功用于定量风险分析应用程序,概率安全评估(PSA)。监管机构(如印度的AERB)现在已经接受数据库的重要性和使用,这是工业实践中核工业安全性和可靠性研究的基础。包含人为错误数据的数据库源于核工业进行的研究,并与设备故障模型一起用于评估核电厂运行的总体安全水平。基于这些数据库,非常强大的风险分析和可靠性工程方法(例如故障和事件树方法)用于定量确定工厂运行中存在的安全性,可靠性和性能水平以及应将改进资源应用于何处。此外,已经识别并鼓励使用风险告知方法,以作为更有效地改善站台资源管理的一种选择,并且该技术已经在使用中的检查和测试领域中取得了显著成功。但是,对于任何分析而言,大型数据库是必须的。因此,数据汇编是PSA的关键要素,必须获得PSA的真实图片和真实结果。本文介绍了拉贾斯坦邦原子能发电站3&4机组遵循的有关从计算机维护管理系统(CMMS)收集数据的实践,这是一个基于缺陷报告的系统,其中提出了缺陷,并对其进行了后续跟进直到他们整改。在报告缺陷后,由维修机构申请工作许可证,这些许可证随后由运营部门签发,并在纠正缺陷后最终由维修机构交出。适当的原因代码,故障代码和完成的工作历史记录保存在CMMS数据库中,这些代码因包含在P- -- SA模型。

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