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Application of Ex-Vessel Neutron Dosimetry Combined with In-core Measurements for Correction of Neutron Source Used for Reactor Pressure Vessel Fluence Calculations

机译:船外中子剂量学与堆芯内测量相结合在反应堆压力容器注量计算中所用中子源校正中的应用

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This paper deals with calculated and semi-analytical evaluations of VVER-1000 reactor core neutron source distributions and their influence on measurements and calculations of the integral through-vessel neutron leakage. Neutron activation measurements analyzed in the paper were carried out in an ex-vessel air cavity at different nuclear power plant units with VVER-1000 during different fuel cycles. The time-integrated neutron source distributions used for DORT calculations were prepared via two different approaches based on (a) calculated fuel burnup (standard routine procedure) and (b) in-core measurements by means of self-powered detectors (SPDs) and thermocouples (TCs) (new approach). Considering that fuel burnup distributions in operating VVER may be evaluated now by the use of analytical methods (calculations) only, it is necessary to develop new approaches for the testing and correction of calculated evaluations of a neutron source. The results presented in this paper allow one to consider the reverse task of the alternative estimation of fuel burnup distributions. The proposed approach is based on the adjustment (fitting) of time-integrated neutron source distributions, and thus fuel burnup patterns, in some part of the reactor core, taking into account neutron leakage measurements, neutron-physical calculations, and in-core SPD and TC measurement data.
机译:本文讨论了VVER-1000反应堆堆芯中子源分布的计算和半分析评估,以及它们对整体贯穿式中子泄漏测量和计算的影响。本文中分析的中子活化测量是在不同的燃料循环中,在不同核电站单位的VVER-1000的前舱空气腔中进行的。用于DORT计算的时间积分中子源分布是基于(a)计算出的燃料燃耗(标准例行程序)和(b)利用自供电探测器(SPD)和热电偶进行的堆芯内测量通过两种不同的方法准备的(TC)(新方法)。考虑到现在只能通过使用分析方法(计算)来评估运行中的VVER中的燃耗分布,因此有必要开发新的方法来测试和校正中子源的计算评估。本文介绍的结果使我们可以考虑燃料燃耗分布的替代估计的相反任务。所提出的方法基于对时间积分中子源分布的调整(拟合),并因此基于反应堆堆芯某些部分的燃料燃耗模式,同时考虑了中子泄漏测量,中子物理计算和堆芯SPD和TC测量数据。

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