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Quantitative Analysis of Effect of Power Uprate on Core Damage Frequency of MBLOCA

机译:功率提升对MBLOCA核心损坏频率影响的定量分析

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During past years, a large number of nuclear power plants have undergone significant modifications. Plant modifications can affect the safety characteristics that should be evaluated quantitatively. A methodology combining probabilistic and deterministic approaches has been proposed by an expert group named Safety Margin Action Plan (SMAP) to quantify the impact of the plant modification, and the follow-up expert group, Safety Margin Application and Assessment (SM2A), has built up a pilot study to demonstrate the methodology suggested by SMAP. In this paper, the impact of the plant modification on the core damage frequency of a medium-break loss-of-coolant-accident (MBLOCA) is presented as a result of the pilot study carried out in the framework of SM2A. The Zion nuclear power plant and a hypothetical power uprate of 10 % have been selected as a reference plant and modification, respectively. The event postulated for the analysis is a cold leg break with a size of 10 in. The peak cladding temperature has been suggested as a relevant figure of merit as a proxy for core damage. A dominant sequence in the event tree of MBLOCA has been chosen according to the selection criteria suggested by SM2A. The thermal hydraulic calculation has been performed by using TRACE code and the best estimate plus uncertainty (BEPU) methodology has been employed to reduce unnecessary conservatism from the thermal hydraulic analysis and to generate the probability distribution of the figure of merit. Since the operator action for the recirculation cooling dominantly influences the consequences of the reference sequence, the operator action has been modeled using a distribution of the operator action time and is therefore sampled stochastically. In order to estimate the effect of the operator action and power uprate precisely, a stratified sampling of the operator action time over a time window of interest in which both sequence success and failure can coexist is used. A methodology to quantify the change of core damage frequency has been proposed. Its application indicates that the core damage frequency (CDF) can be estimated more realistically by the reduction of some conservatisms and the CDF by a MBLOCA is increased by 58.5 % as a response of a hypothetical power uprate of 10 %.
机译:在过去的几年中,许多核电厂都进行了重大修改。工厂改造会影响应定量评估的安全特性。名为安全边际行动计划(SMAP)的专家组提出了一种将概率和确定性方法相结合的方法,以量化工厂改造的影响,而后续专家组安全边际应用和评估(SM2A)已建立进行了一项初步研究,以证明SMAP建议的方法。本文是在SM2A框架下进行的初步研究的结果,介绍了工厂改造对中度破损冷却剂事故(MBLOCA)核心损坏频率的影响。锡安核电站和假设的10%功率提升率分别被选作参考电站和改型。假定用于分析的事件是一个10英寸大小的冷断腿。建议将包层的最高温度作为相关的性能指标,以替代核心损坏。 MBLOCA事件树中的主导序列已根据SM2A建议的选择标准进行选择。通过使用TRACE代码执行热力水力计算,并采用最佳估计加不确定度(BEPU)方法来减少热力水力分析中不必要的保守性,并生成品质因数的概率分布。由于用于再循环冷却的操作员动作主要影响参考序列的结果,因此已经使用操作员动作时间的分布对操作员动作进行了建模,因此进行了随机采样。为了精确地估计操作员动作的影响和功率提升,使用了在感兴趣的时间窗口内对操作员动作时间进行分层采样的方法,在该时间窗口中,序列成功和失败都可以共存。已经提出了量化核心损坏频率变化的方法。它的应用表明,通过减少一些保守性,可以更现实地估算核心损坏频率(CDF),并且MBLOCA的CDF可以提高58.5%,这是假设功率提升率为10%的结果。

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