基于组件计算的燃耗实验基准题建模分析

Modeling and analysis of depletion experiment benchmark based on assembly calculation

组件计算在堆芯核设计中占有重要地位。组件程序的燃耗计算精度对核反应堆堆芯的功率分布、换料寿期及反应性控制设计方面具有重要意义。为了评估用于堆芯燃耗计算的多群常数库的准确性,本文运用DRAGON计算程序建立了燃耗实验计算模型,采用SFCOMPO-2.0燃耗实验基准题提供的乏燃料样品燃耗历史参数及最终核素组分信息,对Takahama-3反应堆、H.B.Robinson-2反应堆及Beznau-1反应堆系列样品进行了建模计算,并将计算结果与SFCOMPO-2.0数据库中的基准实验结果进行了对比和分析。结果表明:多数核素的模拟结果与基准值符合良好,误差在10%以内。同时本文对理论计算值与基准实验值存在差异较大的几种核素进行了相应讨论,并对样品计算结果进行了对比分析。

[Background]Assembly calculation plays an important role in reactor core design.The depletion calculation accuracy of the assembly calculation is of great significance to the power distribution,refueling life and reactivity control design of nuclear reactor core.[Purpose]This study aims to evaluate the accuracy of the multigroup constant library in the neutron depletion calculation and establish a set of depletion experimental calculation model.[Methods]The depletion historical parameters and the final nuclide composition information were provided by the SFCOMPO-2.0 database.The information of the Takahama-3 reactor,H.B.Robinson-2 reactor and Beznau-1 reactor samples were modeled using the DRAGON code.Some simplified methods were applied to some unavailable data information.The numerical results were compared and analyzed with the benchmark results in the SFCOMPO-2.0 database.[Result&Conclusions]The results show that most of the nuclide productions are in good agreement with the reference value,and the errors are within 10%.Nuclides with large differences between numerical results and benchmark results are discussed simultaneously,and computational results of three reactor samples were compared and analyzed.