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APPLICATION OF SMAP METHODOLOGY TO A10 POWER UP-RATE FOR ZION NPP SBO TRANSIENT

机译:SMAP方法在锡安NPP SBO暂态A10%功率提升率中的应用

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During the past years, nuclear power plants underwent some major changes in their design and operation mode to fulfill new objectives, such as power up-rate, life extension and/or increased fuel burn up. While fulfilling all the regulatory requirements, these changes - not necessarily and/or completely accounted for in the original design - can challenge the plant safety margins and induce a potential increase of the risk. In order to assess the impact of such modifications on the safety margins, the Committee on the Safety of Nuclear Installations (CSNI) approved in December 2003 a Safety Margins Action Plan (SMAP) and established an international Working Group aimed at developing a new methodology to address the problem, which has been successfully done [1].Then, the CSNI mandated a SM2A (Safety Margin, Assessment and Application) group to apply the SMAP methodology to a real case. A 10% power up-rate for Zion PWR has been selected as NPP modification and the increase of Core Damage Frequency (CDF) was selected as a metric for change in safety margin appraisal.A Probabilistic Safety Analysis - based (PSA) investigation phase, shared by the organizations participating in the group, aimed at selecting the event trees and the main sequences, which the change could potentially affect in a significant way. It was agreed that, once the selection done, calculations had to be run to quantify the effects.The reference PSA for Zion NPP used in the exercise was performed in the framework of NUREG 1150. For the SM2A exercise it was agreed that the risk measure is CDF. IRSN was in charge of the Loss Of offSite Power (LOSP) event trees. In this family of events it appeared that 2 sequences correspond to the conditions (a potential effect with a non negligible probability). These 2 selected sequences were Station Black Out (SBO) scenarios: SBO with loss of Auxiliary Feed Water (AFW) and SBO with a seal Loss Of Coolant Accident (LOCA).This paper describes the PSA based sequences selection and the preparation of the input desks for CATHARE code, presents the assumptions of modeling, and discusses the numerical results for those two scenarios. The Peak Cladding Temperature (PCT) being the safety variable of interest, it appears that it is sensitive to the power increase only in the first scenario (SBO-AFW). For this case, an uncertainty analysis has been carried out, too, in order to assess the increase of CDF. Its main findings are discussed in the paper.
机译:在过去的几年中,核电厂在设计和运行方式上进行了一些重大更改,以实现新的目标,例如提高功率,延长使用寿命和/或增加燃料消耗。在满足所有法规要求的同时,这些更改(未必和/或未在原始设计中完全考虑)会挑战工厂的安全范围,并可能导致风险增加。为了评估此类修改对安全裕度的影响,核装置安全委员会(CSNI)于2003年12月批准了《安全裕度行动计划》(SMAP),并成立了一个国际工作组,旨在开发一种新的方法来解决已经成功完成的问题[1]。 然后,CSNI委托一个SM2A(安全裕度,评估和应用)小组将SMAP方法应用于实际案例。 Zion PWR的10%功率提升率已被选作NPP修改,铁心损坏频率(CDF)的增加已被选作安全裕度评估变化的指标。 参与该组织的组织共享一个基于概率安全分析(PSA)的调查阶段,旨在选择事件树和主要顺序,这些变更可能会对重大影响。商定,一旦选择完成,就必须进行计算以量化影响。 演习中使用的Zion NPP的参考PSA在NUREG 1150框架中进行。对于SM2A演习,已商定风险度量为CDF。 IRSN负责场外电源丢失(LOSP)事件树。在这一系列事件中,似乎有2个序列与条件相对应(潜在影响且概率不可忽略)。这2个选定的序列是停电(SBO)场景:SBO带有辅助给水(AFW)丢失和SBO带有密封冷却液事故(LOCA)。 本文介绍了基于PSA的序列选择和CATHARE代码输入台的准备工作,提出了建模假设,并讨论了这两种情况的数值结果。峰值熔覆温度(PCT)是关注的安全变量,似乎仅在第一种情况(SBO-AFW)中它才对功率增加敏感。对于这种情况,还进行了不确定性分析,以评估CDF的增加。本文讨论了其主要发现。

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