ABSTRACT

To extend the information on the validation of the JENDL-4.0 nuclear data library, continuous-energy Monte Carlo calculation was applied to the analysis of the measured core radial fission rate distributions in the light-water-moderated cores loaded with mixed oxide (MOX) and UO₂ fuel rods. The measured results were taken from the reports of the critical experiments performed using the Tank-type Critical Assembly (TCA) of the Japan Atomic Energy Agency in the 1970s. The PuO₂ contents of the MOX fuel ranged from 1.14 wt% to 3.37 wt% and the enrichments of the UO₂ fuel from 1.180 wt% to 2.596 wt%. The lattice pitches were from 1.660 cm to 1.956 cm. A half number of cores in the analyzed 30 cores were mainly loaded with the MOX fuel rods and the others were the MOX-UO₂ mixed cores or the UO₂ cores. The calculated results generally well reproduced the measured fission rates of the MOX and UO₂ fuel rods in the test fuel assemblies and those in the x-direction and diagonal direction of the cores.

摘要

为了扩展有关 JENDL-4.0 核数据库验证的信息，连续能量蒙特卡罗计算被应用于对加载混合氧化物 (MOX) 的轻水慢化堆芯中测得的堆芯径向裂变率分布的分析和UO ₂燃料棒。测量结果取自 1970 年代使用日本原子能厅的罐式临界组件 (TCA) 进行的临界实验报告。MOX 燃料的 PuO ₂含量范围从 1.14 wt% 到 3.37 wt%，而 UO ₂的富集燃料从 1.180 wt% 到 2.596 wt%。晶格间距从 1.660 厘米到 1.956 厘米。在所分析的 30 个堆芯中，一半数量的堆芯主要装载 MOX 燃料棒，其余为 MOX-UO ₂混合堆芯或 UO ₂堆芯。计算结果总体上很好地再现了测试燃料组件中MOX和UO ₂燃料棒的裂变速率以及堆芯x方向和对角线方向的裂变速率。