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Development of a versatile depletion code AMAC
Annals of Nuclear Energy ( IF 1.9 ) Pub Date : 2020-08-01 , DOI: 10.1016/j.anucene.2020.107446
Binhang Zhang , XianBao Yuan , Yonghong Zhang , Haibo Tang , Liangzhi Cao

Abstract The reactor fuel consumption calculation is an important part of reactor design and analysis, which usually needs to be completed iteratively by transport calculations and point-depletion calculations. AMAC is a newly versatile point-depletion and radioactive-decay code for use in simulation nuclear fuel cycles and calculating the nuclide compositions and radiation characteristics of materials. The code implements two depletion algorithms to treat the stiff depletion systems, including Transmutation trajectory analysis (TTA) method and Chebyshev rational approximation method (CRAM). With different higher-order approximations, the IPF form of CRAM is implemented to meet the high-precision requirements for the decay calculation of long-term nuclide system. And the accuracy analysis of higher-order CRAM is also discussed in the paper. In addition, the calculation of material radiation characteristics can be provided in AMAC to extend the application in different computational and analytical requirements. Then based on the complex nuclide system and a series of efficient programming methods, the high precision and efficiency of point-depletion calculation can be guaranteed. Three different calculation modes are supported by AMAC to execute the decay, constant flux and constant power calculations. By comparing with ORIGEN and FISPACT, the performance of AMAC in nuclide compositions and varieties of material radiation characteristics is proved and discussed. Furthermore, by coupling OpenMC and AMAC, the OECD/NEA burnup credit criticality benchmark and IAEA-ADS benchmark are used to validate the code performance of efficiency and precision in coupling calculations. All the results have shown good agreements with reference values and other codes, which demonstrates AMAC is a potential tool for accurate depletion calculation of reactors.

中文翻译:

通用耗尽码AMAC的开发

摘要 反应堆燃料消耗计算是反应堆设计和分析的重要组成部分,通常需要通过输运计算和点消耗计算迭代完成。AMAC 是一种新的多功能点消耗和放射性衰变代码,用于模拟核燃料循环和计算材料的核素成分和辐射特性。该代码实现了两种耗尽算法来处理刚性耗尽系统,包括嬗变轨迹分析(TTA)方法和切比雪夫有理逼近方法(CRAM)。通过不同的高阶近似,实现了 CRAM 的 IPF 形式,以满足长期核素系统衰变计算的高精度要求。文中还讨论了高阶CRAM的精度分析。此外,AMAC 中可以提供材料辐射特性的计算,以扩展在不同计算和分析要求中的应用。然后基于复杂的核素系统和一系列高效的编程方法,可以保证点耗尽计算的高精度和效率。AMAC 支持三种不同的计算模式来执行衰减、恒定通量和恒定功率计算。通过与ORIGEN和FISPACT的比较,证明和讨论了AMAC在核素组成和各种材料辐射特性方面的性能。此外,通过耦合 OpenMC 和 AMAC,使用 OECD/NEA 燃尽信用临界性基准和 IAEA-ADS 基准来验证耦合计算中的效率和精度的代码性能。
更新日期:2020-08-01
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