原子能科学技术 ›› 2022, Vol. 56 ›› Issue (5): 952-960.DOI: 10.7538/yzk.2021.youxian.0872

• 核数据宏观参数制作与检验 • 上一篇    下一篇

燃耗数据库基准检验方法研究

肖越;吴海成;吴小飞;张环宇   

  1. 中国原子能科学研究院 核数据重点实验室,中国核数据中心,北京102413
  • 出版日期:2022-05-20 发布日期:2022-05-20

Research on Benchmarking Method of Burnup Database

XIAO Yue;WU Haicheng;WU Xiaofei;ZHANG Huanyu   

  1. China Nuclear Data Center, Key Laboratory of Nuclear Data, China Institute of Atomic Energy, Beijing 102413, China
  • Online:2022-05-20 Published:2022-05-20

摘要: 燃耗数据库基准检验方法对于研制高准确度的燃耗数据库至关重要。本文以TAKAHAMA3压水堆辐照后检验实验中SF95样品的建模为例,研究了建模要素对燃耗计算的影响,确定了燃耗实验建模的方法,开展了燃耗信用制研究感兴趣的锕系和裂变产物核素积存量计算值与实验值的比对。比对结果显示,主锕系核素计算偏差小于2%,大部分次锕系核素偏差小于10%,大部分重要裂变产物核素偏差小于5%。本文还对125Sb积存量随燃耗深度变化规律进行了理论分析,确认了破坏性放化实验测量结果存在缺陷,并进一步获得了125Sb积存量的修正值,使计算偏差从接近170%下降到20%以内。本次研究表明,燃耗数据库基准检验研究不仅需发展适当的燃耗实验建模方法,还需对实验数据进行适当的评价。

关键词: 燃耗分析, 燃耗数据库基准检验, 实验值修正

Abstract: The development of high precision burnup analysis requires high accuracy burnup database. The benchmarking method of burnup database is very important for developing high accuracy burnup database. Based on the burnup database composed of the multitemperature continuous point section database CENACE13 made by China Nuclear Data Center and Cinder90 burnup database, the modeling of SF95 samples in the post irradiation experiment of TAKAHAMA3 power water reactor was taken as an example. The spent fuel composition database SFCOMPO20 gives the detailed information of postirradiation experiment of TAKAHAMA3 power water reactor, including component information, power history, boron concentration history and nuclides inventory value. The influence of modeling elements on burnup calculation was studied, and the modeling method of burnup benchmark experiment was determined. The influence of modeling elements such as material temperature and density, boron concentration and burnup step on modeling calculation was determined. As an important part of burnup credit, burnup analysis aims to obtain the nuclide composition and inventory of spent fuel. Using the burnup benchmark experimental modeling method, the burnup credit was studied and the comparison of calculated values and experimental values of interested actinide nuclides and fission products nuclides was carried out. The preliminary results showed that the deviation between the calculated values and the experimental values of main actinide nuclides is less than 2%, the relative deviation between the calculated values and the experimental values of most minor actinides nuclides is less than 10%, and the deviation between the calculated values and the experimental values of most important fission products nuclides is less than 5%. In this paper, based on the adjacent burnup chain of 125Sb, the variation law of 125Sb inventory with burnup depth was theoretically analyzed, and it is confirmed that there are defects in the measurement results of destructive radiochemical experiment. In this study, the destructive experimental value of 125Sb was modified by nondestructive experimental measurement value and experimental value modification formula. And the corrected experimental values of 125Sb inventory were obtained, which reduced the calculation deviation between calculated value and experimental value from nearly 170% to less than 20%. This study shows that the benchmarking of burnup database using the spent fuel composition database requires not only the appropriate burnup benchmark experimental modeling method, but also the appropriate evaluation and verification of inventory measurement data, so as to be able to be used for benchmarking of burnup database and burnup credit research.

Key words: burnup analysis, benchmark verification of burnup database, correction of experimental value