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LOCA Event Tree Analysis for Qinshan Phase HI CANDU-6 PHWR NPP

机译:lo CA event tree analysis for Q in山phase HIC and U-6 pH W RN PP

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摘要

Qinshan Phase III is the first commercial pressurized heavy water reactor (PHWR) NPP in China, and it uses CANDU-6 design developed by AECL. Based on plant design and operation experience, the event tree analysis model has been developed for both small break LOCA (SB-LOCA) and large break LOCA (LB-LOCA), which is an important aspect of operational Probabilistic Safety Assessment (PSA). Both SB-LOCA and LB-LOCA event tree analysis have been performed for Qinshan Phase III CANDU-6 PHWR NPP (TQNPC). And the event sequence development and plant damage status (PDS) were provided in the analysis. It reflects actual plant configuration and response under a certain event, and various break type and locations were also considered in the event tree analysis, e.g. Pressure Tube Rupture, Pressure Tube and Calandria Tube Rupture, Feeder Breaks, Pressurizer Relief/Steam Bleed Valves Fail Open, Liquid Relief Valves Fail Open, etc.
机译:秦山三期是中国第一座商用加压重水反应堆(PHWR)核电站,采用了AECL开发的CANDU-6设计。基于工厂设计和运营经验,已经针对小中断LOCA(SB-LOCA)和大中断LOCA(LB-LOCA)开发了事件树分析模型,这是运行概率安全评估(PSA)的重要方面。秦山三期CANDU-6 PHWR NPP(TQNPC)已进行了SB-LOCA和LB-LOCA事件树分析。分析中还提供了事件序列发展和植物危害状况(PDS)。它反映了特定事件下的实际工厂配置和响应,并且在事件树分析中还考虑了各种中断类型和位置,例如压力管破裂,压力管和Calandria破裂,供料器断裂,增压器安全阀/蒸汽放气阀故障打开,液体安全阀故障打开等。

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