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首页> 外文会议>PHYSOR 2004 - the physics of fuel cycles and advanced nuclear systems: global developments >Analysis of SNEAK-7A 7B Critical Benchmarks using 3-D DeterministicTransport and Sensitivity Analysis Methods
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Analysis of SNEAK-7A 7B Critical Benchmarks using 3-D DeterministicTransport and Sensitivity Analysis Methods

机译：使用3-D确定性传输和灵敏度分析方法分析SNEAK-7A和7B关键基准

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摘要

As the detailed information on critical experiments performed in thernSNEAK facility became available in the framework of the InternationalrnReactor Physics Benchmark Experiments (IRPhE) project, SNEAK-7A & 7Brncritical benchmarks are re-evaluated. The realistic modeling of thesernassemblies was done using the DANTSYS code capability for X-Y-Zrngeometry. Predicted core eigenvalues, spectral indices, and central materialrnworths with effective cross sections based on JEF-2.2 nuclear data file, havernbeen compared with measured values. As a result, the capability of modernrn3-D transport method featuring very small corrections to the raw calculatedrnvalue is appreciated and the quality of basic library for the interestedrnassemblies is assessed. In addition, the core eigenvalue sensitivity analysis tornthe basic cross section of each important nuclide is performed. By utilizingrnthe deviation of calculated spectrum indices from the measurement, togetherrnwith the sensitivity coefficient, it is shown how the sensitivity analysis can bernusefully adopted to figure out a specific detail of basic cross section forrnimprovement and investigate the quality of measured integral parameters.
机译：当在国际反应堆物理基准实验（IRPhE）项目的框架中获得有关在rnSNEAK设施中进行的关键实验的详细信息时，将重新评估SNEAK-7A和7Brncritical基准。使用DANTSYS代码功能对X-Y-Zrngeometry进行实际的装配体建模。已将基于JEF-2.2核数据文件的预测核心特征值，光谱指数和具有有效横截面的中心材料值与测量值进行了比较。结果，赞赏了对原始计算值进行非常小的校正的现代3-D传输方法的能力，并评估了感兴趣的组件的基本库的质量。此外，还对每个重要核素的基本截面进行了核心特征值敏感性分析。通过利用计算出的光谱指数与测量值的偏差以及灵敏度系数，显示了如何有效地利用灵敏度分析来找出基本截面改进的具体细节，并研究所测积分参数的质量。

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