首页> 外文会议>International Conference on Probabilistic Safety Assessment and Management(PSAM7-ESREL'04) v.4; 20040614-20040618; Berlin; DE >Reliability Control of Coolant Measure System in RBMK-1500 Reactor Using Preventive Maintenance
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Reliability Control of Coolant Measure System in RBMK-1500 Reactor Using Preventive Maintenance

机译:基于预防性维护的RBMK-1500反应堆冷却剂测量系统的可靠性控制

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摘要

The reliability of a system, which is designed for measurement of coolant flow through fuel channels in Ignalina nuclear power plant RBMK-1500 reactors, is considered. Existing flowmeters degradation level assessment criteria has been analysed and new mathematical model for assessment of degradation level is presented.
机译:考虑了用于测量伊格纳利纳核电站RBMK-1500反应堆中通过燃料通道的冷却剂流量的系统的可靠性。分析了现有流量计的退化水平评估标准,提出了评估退化水平的新数学模型。

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