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Code improvement and model validation for Asco-II Nuclear Power Plant model using a coupled 3D neutron kinetics/thermal-hydraulic code

机译:使用耦合3D中子动力学/热液压代码对asco-II核电站进行代码改进和模型验证

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摘要

This paper provides a Best Estimate validation calculation with a coupled thermal–hydraulic and 3D neutron kinetic model for Ascó-II Nuclear Power Plant. Common NRC codes have been used for its purpose. TRACE is the code used for the thermal–hydraulic system calculations; PARCS is the code used for the 3D neutron kinetics calculations. Cross section calculations were performed with the HELIOS lattice physics code, finally GenPMAXS was used to convert the cross section into the PARCS format. A simplified three dimensional 3D neutronics model of the Ascó II NPP is used as a core kinetics model. A 3D cylindrical thermal–hydraulic vessel plus 1D representation of the remainder of the full plant model is used as the thermal–hydraulic model. The transient selected to ensure the model validation is an actual 50% Loss of Load. This transient is characterized by space–time effects and was used to validate different thermal–hydraulic system models for the GET university group in the past. The scenario is also good to ensure the validation of a coupled 3D neutron kinetics code since it provides a transient situation between two stable regions at 100% and 50%. From the current code versions used, some source code modifications have been carried out in order to ensure the correct feedback between thermal–hydraulic and neutron kinetics code. In that sense, a dynamic control rod movement between TRACE and PARCS has been implemented. This is a complete control rod position feedback during transient scenarios. After all the work was performed, the important TH and NK time trend parameters were compared to the plant data and the comparison was reasonable with some discrepancy, thus the developed system models and the code modifications are robust enough to be used for future safety analysis. New coupled code capability has been tested and found as a required capability, when validating 3D NK–TH coupled calculations.
机译:本文为Ascó-II核电厂提供了一个最佳热值验证计算方法,并结合了热工和3D中子动力学模型。常用的NRC代码已用于其目的。 TRACE是用于热工-液压系统计算的代码; PARCS是用于3D中子动力学计算的代码。使用HELIOS晶格物理代码进行横截面计算,最后使用GenPMAXS将横截面转换为PARCS格式。 AscóII NPP的简化三维3D中子学模型被用作核心动力学模型。 3D圆柱热工液压容器加上完整工厂模型其余部分的1D表示用作热工液压模型。为确保模型验证而选择的瞬态是实际的50%负载损失。这种瞬态具有时空效应的特征,过去曾被用于验证GET大学集团的不同热工-液压系统模型。该场景还可以确保耦合3D中子动力学代码的验证,因为它提供了两个稳定区域之间100%和50%的瞬态情况。从当前使用的代码版本开始,已对源代码进行了一些修改,以确保热工液压代码和中子动力学代码之间的正确反馈。从这个意义上说,已经实现了TRACE和PARCS之间的动态控制杆运动。这是瞬态情况下的完整控制杆位置反馈。完成所有工作后,将重要的TH和NK时间趋势参数与工厂数据进行比较,并且比较合理,但存在一些差异,因此开发的系统模型和代码修改足够强大,可用于将来的安全性分析。在验证3D NK-TH耦合计算时,已经测试了新的耦合代码功能,并将其作为必需功能。

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