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ANALYSIS OF A CRDM NOZZLE BREAK LOCA WITHOUT SCRAM USING THE U.S. NRC COUPLED CODE TRAC-M/PARCS

机译:使用美国NRC耦合代码TRAC-M / PARC而没有扰流的CRDM喷嘴破坏基因座的分析

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Recently, through-wall circumferential cracks in several control rod drive mechanism (CRDM) nozzle penetrations were detected at the Oconee-3 nuclear power plant. The presence of these cracks was seen as a potential precursor to a small break loss of coolant accident. In order to assess the impact of a postulated failure of a CRDM housing, analyses were performed using the U.S. NRC coupled thermal-hydraulics and neutronics code TRAC-M/PARCS. Although deemed highly unlikely, it was assumed that no control rods inserted in order to bound any possible reactivity transient associated with the break. The thermal-hydraulic model used to perform the study is based on an existing model of Oconee, built for PTS analysis, which models the whole plant and some of its control systems. A refined vessel model based on a TMI model was used to increase the resolution of the results and facilitate coupling to PARCS. All relevant ECCS systems were modeled and the control system allowed for, in addition to automatic actions, some assumed operator intervention. In particular, HPI throttling was modeled to maintain the hot leg subcooled at 42 +/- 7 K, and prevent an excessive amount of cold water from being injected into the system. A spatial kinetics analysis of this event was necessary because of the wide range of core conditions which occurred during the transient, from hot full power operation conditions to the cold zero power shutdown state. Analysis of the event with point kinetics and "best estimate" reactivity coefficients resulted in significant miss-prediction of the core power response. Conversely, the three-dimensional kinetics solution with cross section data generated over the entire range of the event led to a more accurate calculation of the power response and the overall analysis of the system transient response. This paper will describe the analysis of the control rod drive nozzle break event without scram using TRAC-M/PARCS.
机译:最近,在OConee-3核电站检测到几种控制杆驱动机构(CRDM)喷嘴穿透的通壁周向裂缝。这些裂缝的存在被视为潜在的前体,对冷却剂事故的小突破。为了评估CRDM壳体假设失效的影响,使用美国NRC耦合的热液压和中子码Trac-M / PARC进行分析。尽管非常不可能地认为,但是假设没有插入的控制杆以便与断裂相关的任何可能的反应性瞬态结合。用于执行该研究的热液压模型基于现有的OCONEE模型,用于PTS分析,该模型为整个工厂和其一些控制系统。基于TMI模型的精制血管模型用于增加结果的分辨率,并促进与PARC的耦合。所有相关的ECCS系统都被建模并允许控制系统,除了自动操作外,还有一些假定的操作员干预。特别地,模拟HPI节流以将热腿部加热在42 +/- 7 k下,并防止过量的冷水注入系统中。由于在瞬态期间发生的核心条件,从热的全电源运行条件到冷零功率关断状态,因此需要对该事件的空间动力学分析是必要的。用点动力学和“最佳估计”反应性系数的事件分析导致核心功率响应的显着错过预测。相反,具有在事件的整个范围内产生的横截面数据的三维动力学解决方案导致了更准确的功率响应计算和系统瞬态响应的总体分析。本文将描述无需使用Trac-M / PARC的扰流的控制杆驱动喷嘴断开事件的分析。

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