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首页> 外文期刊>Journal of nuclear science and technology >Isotopic Analysis of Actinides and Fission Products in LWR High-Burnup UO_2 Spent Fuels and its Comparison with Nuclide Composition Calculated Using JENDL, ENDF/B, JEF and JEFf
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Isotopic Analysis of Actinides and Fission Products in LWR High-Burnup UO_2 Spent Fuels and its Comparison with Nuclide Composition Calculated Using JENDL, ENDF/B, JEF and JEFf

机译：轻水堆高爆炸UO_2乏燃料中Act系元素和裂变产物的同位素分析及其与使用JENDL，ENDF / B，JEF和JEFf计算的核素组成的比较

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A chemical isotopic analysis of the actinides and fission products of a high-burnup PWR-UO2 fuel with an average burnup of 60.2 MWd/kgHM was carried out to accumulate extensive nuclide composition data. Furthermore, computational analysis was performed using the integrated burnup calculation code SWAT. The differences between the amounts obtained by the chemical isotopic analysis and SWAT calculation using JENDL-3.2, JENDL-3.3, ENDF/B-VI.5, ENDF/B-VI.8, JEF-2.2 and JEFF-3.0 were evaluated as the ratios of the calculated values to the experimental values (C/E ratios). For actinides, the calculated ~(244)Cm amount, which is an important nuclide as a major neutron source in spent fuels, was underestimated. The main sensitive path for ~(244)Cm was therefore investigated by a simple depletion calculation for actinides and the cause of the underestimation of the calculated ~(244)Cm amount is discussed. The fission products ~(88)Sr,~(90)Sr, ~(89)Y, ~(106)Ru, ~(133)Cs, ~(135)Cs and ~(144)Nd, for which the C/E ratios were larger than 1.05 or smaller than 0.95, were investigated to improve their C/E ratios by a simple depletion calculation with simplified burnup chains and sensitivity coefficients, and the correction values for the fission yields or capture cross sections were estimated. The effect of power history on nuclide composition was also investigated. Additionally, the fission products for which the C/E ratios strongly depend on the type of library are discussed using sensitivity coefficients.
机译：对高燃耗PWR-UO2燃料（平均燃耗为60.2 MWd / kgHM）的the系元素和裂变产物进行化学同位素分析，以积累大量的核素组成数据。此外，使用集成的燃耗计算代码SWAT进行了计算分析。通过化学同位素分析和使用JENDL-3.2，JENDL-3.3，ENDF / B-VI.5，ENDF / B-VI.8，JEF-2.2和JEFF-3.0的SWAT计算获得的量之间的差异被评估为计算值与实验值之比（C / E比）。对于act系元素，低估了〜（244）Cm的计算量，这是一种重要的核素，是乏燃料中的主要中子源。因此，通过简单的calculation系元素耗尽计算研究了〜（244）Cm的主要敏感路径，并讨论了低估〜（244）Cm量的原因。裂变产物〜（88）Sr，〜（90）Sr，〜（89）Y，〜（106）Ru，〜（133）Cs，〜（135）Cs和〜（144）Nd，其C / E比值大于1.05或小于0.95，通过简单的耗竭计算和简化的燃耗链和灵敏度系数进行研究，以提高其C / E比值，并估算了裂变产率或俘获截面的校正值。还研究了功率历史对核素组成的影响。此外，使用敏感性系数讨论了C / E比强烈取决于库类型的裂变产物。

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