Effects of evaluated nuclear data libraries on the calculation results for fuel burnup with minor actinides in a VVER reactor

Gleb W. Karpovich, Yury A. Kazansky, Kirill A. Bakhantsov, Kirill A. Isanov, Nikita O. Kushnir
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Abstract

The paper deals with assessing the effects of the ENDF/B-VI.8, ENDF/B-VII.0, JEFF 3.1 and JEFF 3.1.1 nuclear data libraries on the results of calculating a number of functionals for a system based on a VVER reactor with fuel with a large fraction of minor actinides (up to 10%). Key estimates have been obtained for the errors introduced by libraries in calculations of systems with minor actinides (MA) based on a VVER-1200 reactor: – for reactivity, σ ρ = 0.3 β eff ; – for isotopic compositions with minor actinides, ≤ 5% (the error for each particular isotope is different); – for the total mass of accumulated MAs, ε m = 0.8%. Conclusions have been made with respect to the need for the further refinement of the library MA data proceeding from the nature of the calculation tasks that dictate the requirements for the accuracy of nuclear constants. It has been shown that systems based on VVER-1000/1200/1300 reactors with MAs need to be calculated using several libraries of evaluated nuclear data created at different organizations and based on the largest possible number of non-recurrent sets of experimental data.
在VVER反应堆中少量锕系元素燃料燃耗计算结果的评估核数据库Effects
本文讨论了评估ENDF/B-VI的影响。8日,ENDF / B-VII。0、JEFF 3.1和JEFF 3.1.1核数据库对基于含有大量微量锕系元素(高达10%)燃料的VVER反应堆系统的若干函数的计算结果。对基于VVER-1200反应器计算含微量锕系元素(MA)体系时,库引入的误差进行了关键估计:反应性为-,σ ρ = 0.3 β eff;-对于含有少量锕系元素的同位素组成,误差≤5%(每种特定同位素的误差不同);-为累积MAs的总质量,ε m = 0.8%。从决定核常数精度要求的计算任务的性质出发,得出了关于需要进一步改进核常数库数据的结论。已经证明,基于VVER-1000/1200/1300反应堆的系统需要使用不同组织创建的几个评估核数据库,并基于尽可能多的非循环实验数据集来计算。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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