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Analysis and application on sensitivity factors of cross validation of fill rate of CPR1000 unit reactor core coolant monitoring system

机译:CPR1000机组反应堆堆芯冷却液监控系统填充率交叉验证敏感性因素的分析与应用

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The coolant fill rate setting of CPR1000 unit reactor core has train A/B of redundancy measuring channels, whose function is to monitor the water inventory of reactor core under the working conditions of water loss and other accidents to ensure the safety of reactor core. In order to confirm the reliability of train A/B of redundancy measuring channels, a technical solution for the cross comparison of fill rate during the reactor refueling cycle is proposed to validate the consistency of train A/B of redundancy measuring and computing channels. Through the cross validation model of fill rate of reactor core coolant monitoring system, the sensitivity analysis on such input variables as relative pressure of primary coolant circuit, temperature of reactor core, differential pressure of reactor core, absolute pressure of containment, etc. shall be conducted. The sensitivity analysis model adopts the GUM method for the law of propagation of uncertainty, through which the proportion of uncertainty components of various input variables can be obtained. Moreover, the aided analysis based on the engineering statistic data from the nuclear power units of various bases shall be conducted to determine the sensitivity variables of cross validation of fill rate. Based on the combination of variable sensitivity analysis and process variables influence analysis with the switching process of the unit uplink status and the objective law of system change, the optimal window and system condition setting for the redundancy cross validation is proposed, including such factors and statuses as system pressure, temperature, running condition of primary pump, etc. Such solution has been applied to engineering sites, and has achieved good effects which can prove its feasibility and effectiveness. (C) 2019 Elsevier Ltd. All rights reserved.
机译:CPR1000装置反应堆堆芯的冷却水填充率设置具有A / B冗余测量通道,其作用是在失水和其他事故工况下监测反应堆堆芯的水量,以确保反应堆堆芯的安全。为了确认冗余测量通道A / B列的可靠性,提出了一种在反应堆换料周期内交叉比较填充率的技术方案,以验证冗余测量通道和计算通道A / B列的一致性。通过反应堆堆芯冷却液监控系统填充率的交叉验证模型,对一次冷却剂回路的相对压力,反应堆堆芯温度,反应堆堆芯压差,安全壳绝对压力等输入变量进行敏感性分析。进行。灵敏度分析模型采用GUM方法求解不确定性的传播规律,从而可以得出各种输入变量不确定性分量的比例。此外,应根据各基地核电单位的工程统计数据进行辅助分析,以确定填充率交叉验证的敏感性变量。结合变量敏感性分析和过程变量影响分析,结合单元上行状态的切换过程和系统变化的客观规律,提出了冗余交叉验证的最优窗口和系统条件设置,包括这些因素和状态。该解决方案已在工程现场应用,取得了良好的效果,证明了其可行性和有效性。 (C)2019 Elsevier Ltd.保留所有权利。

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