Risk Based Inspection Analysis on Primary and Secondary Cooling Pipe of the TRIGA 2000 Reactor

Zainal Abidin, Hendi Septian Cahyadi, Yayat Supriyatna, A. Sutjipto
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Abstract

Analysis of the application of Risk Based Inspection method in the primary and secondary cooling pipe of TRIGA 2000 Bandung Reactor was conducted with the aim of obtaining a risk level value. To obtain the risk level value is carried out secondary cooling pipe thickness measurement using Ultrasonic Testing first. Furthermore, to obtain the risk level value, data such as pipe specifications, flowing fluid specifications, management system factors, measured pipe thickness data and previous inspection results, and pipe maintenance history will be used to calculate probability of failure (PoF) and Consequence of Failure (CoF) values. Probability of Failure and Consequence of Failure values are then plotted into a risk matrix to find out the level of risk that the component has. Risk level results can then be used to determine inspection methods and inspection intervals. The result of the risk level obtained from the calculation of the primary cooling pipe triga reactor 2000 is MEDIUM, lower than the risk level in the primary cooling pipe Kartini Reactor is MEDIUM HIGH. For the risk level of secondary cooling pipe Triga Reactor 2000 is MEDIUM is the same as the risk level of secondary cooling pipe Kartini Reactor. The recommended inspection methods for both reactors are the same using ultrasonic thickness measurement and visual examination inspection methods. Next inspection intervals for primary cooling pipes were 2068, 2092, 2104, 2110 and 2113 and for Kartini Reactor primary cooling pipes every 20 months. For Secondary cooling pipe Triga Reactor 2000 next inspection interval is 2067, 2090, 2101, 2106 and 2108 and for Kartini Reactor secondary cooling pipe every 10.11 years.
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基于风险的 TRIGA 2000 反应堆一级和二级冷却管检查分析
对 TRIGA 2000 万隆反应堆一级和二级冷却管应用基于风险的检查方法进行了分析,目的是获得风险等级值。为了获得风险等级值,首先使用超声波检测法测量了二级冷却管的厚度。此外,为了获得风险等级值,还将使用管道规格、流体规格、管理系统因素、测量的管道厚度数据和以前的检查结果以及管道维护历史等数据来计算故障概率(PoF)和故障后果(CoF)值。然后将故障概率和故障后果值绘制到风险矩阵中,以找出组件的风险等级。风险等级结果可用于确定检查方法和检查间隔。通过计算得出的一次冷却管 triga 反应堆 2000 的风险等级为中等,低于一次冷却管 Kartini 反应堆的风险等级中等偏上。Triga 反应堆 2000 二次冷却管的风险等级为 MEDIUM,与 Kartini 反应堆二次冷却管的风险等级相同。两个反应堆的建议检查方法相同,均采用超声波测厚和目测检查方法。一级冷却管的下一次检查间隔为 2068、2092、2104、2110 和 2113 个月,Kartini 反应堆一级冷却管的下一次检查间隔为 20 个月。Triga 反应堆 2000 的二级冷却管下一次检查间隔为 2067、2090、2101、2106 和 2108 年,Kartini 反应堆的二级冷却管每 10.11 年检查一次。
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