arXivDaily arXiv每日学术速递 周一至周五更新
arXiv 1507.05892nucl-thphysics.ins-det
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基于单位核相对反应速率不变的局部燃耗计算公式

A simple formula for local burnup based on constant relative reaction rate per nuclei

Cenxi Yuan, Xuming Wang, Shengli Chen

摘要:

本文提出了一个简单的解析公式来解决局部燃耗和同位素分布问题。本方法考虑了中子穿透燃料棒的两种极端情况。在此基础上,得到了计算$^{235}$ U、$^{238}$ U和$^{239}$ Pu反应速率的公式,并直接给出了局部燃耗和同位素分布。从初始燃耗水平开始,将公式的参数拟合到由Monte Carlo(MC)计算给出的反应速率。然后,本公式独立地给出了从开始到高燃耗水平的与MC计算非常相似的结果,但仅需要几分钟。发现相对反应速率几乎不依赖于半径(除了$^{238}$ U的$(n,γ)$)和燃耗,为本公式提供了坚实的背景。当燃料棒位于组件中时,也进行更真实的检查。本公式和MC计算的组合预期在准确性和时间成本上具有良好的平衡。

英文摘要:

A simple and analytical formula is suggested to solve the problems of the local burnup and the isotope distributions. The present method considers two extreme conditions of neutrons penetrating the fuel rod. Based on these considerations, the formula is obtained to calculate the reaction rates of $^{235}$U, $^{238}$U, and $^{239}$Pu and straightforward the local burnup and the isotope distributions. Starting from an initial burnup level, the parameters of the formula are fitted to the reaction rates given by a Monte Carlo (MC) calculation. Then the present formula independently gives very similar results as the MC calculation from the starting to high burnup level, but takes just a few minutes. The relative reaction rates are found to be almost independent on the radius (except $(n,γ)$ of $^{238}$U) and the burnup, providing a solid background for the present formula. A more realistic examination is also performed when the fuel rods locate in an assembly. A combination of the present formula and the MC calculation is expected to have a nice balance on the accuracy and the cost on time.

机构、总结、中文摘要均由AI分析而来,可能存在错误,请以论文正文为准。

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