高温堆临界实验装置ASTRA的初始临界计算

为了验证球床式高温气冷堆初始临界的计算方法,用法国M on te C arlo程序TR IPOL I-4.3对燃料球内的包覆燃料颗粒以及堆芯内不同的球分布进行了模拟。考虑了燃料球的双重非均匀性、不同区域内球的布置以及其在堆芯的体积填充率等。计算了俄罗斯的球床式高温气冷堆临界试验装置A STRA的初始临界。与实验结果比较,计算得到的临界实验高度误差为0.6%,堆芯有效增值因子keff误差为0.1%。TR IPOL I-4.3程序是球床式高温气冷堆初始临界计算的有效工具。

Initial criticality calculation for the high temperature reactor in the ASTRA critical facility

The French Monte Carlo code TRIPOLI-4.3 was used to verify the calculations for the initial core criticality in a pebble-bed high temperature reactor core using various models for discribing the distribution of the coated fuel particles in a fuel pebble and the fuel pebbles in the core.The initial criticality of Russia's high temperature reactor in the ASTRA facility was calculated with considerating the heterogeneity the fuel pebbles,the pebble distributions in different zones,and the pebble packing fraction.The results compared well with experimental results with errors of 0.6% in the initial criticality height and 0.1% in the effective multiplication factor,k__eff.Therefore,the TRIPOLI-4.3 code can accurately calculate the initial criticality of high temperature pebble-bed reactors.