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首页> 外文期刊>Applied radiation and isotopes: including data, instrumentation and methods for use in agriculture, industry and medicine >Analysis of reaction cross-section production in neutron induced fission reactions on uranium isotope using computer code COMPLET
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Analysis of reaction cross-section production in neutron induced fission reactions on uranium isotope using computer code COMPLET

机译：使用计算机代码完成分析中子诱导铀同位素对铀同位素的裂变反应的影响

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摘要

This study provides current evidence about cross-section production processes in the theoretical and experimental results of neutron induced reaction of uranium isotope on projectile energy range of 1-100 MeV in order to improve the reliability of nuclear stimulation. In such fission reactions of U-235 within nuclear reactors, much amount of energy would be released as a product that able to satisfy the needs of energy to the world wide without polluting processes as compared to other sources. The main objective of this work is to transform a related knowledge in the neutron-induced fission reactions on U-235 through describing, analyzing and interpreting the theoretical results of the cross sections obtained from computer code COMPLET by comparing with the experimental data obtained from EXFOR. The cross section value of U-235(n,2n) U-234, U-235(n,3n) U-233, U-235(n, gamma) U-236, U-235(n, f) are obtained using computer code COMPLET and the corresponding experimental values were browsed by EXFOR, IAEA. The theoretical results are compared with the experimental data taken from EXFOR Data Bank. Computer code COMPLET has been used for the analysis with the same set of input parameters and the graphs were plotted by the help of spreadsheet & Origin-8 software. The quantification of uncertainties stemming from both experimental data and computer code calculation plays a significant role in the final evaluated results. The calculated results for total cross sections were compared with the experimental data taken from EXFOR in the literature, and good agreement was found between the experimental and theoretical data. This comparison of the calculated data was analyzed and interpreted with tabulation and graphical descriptions, and the results were briefly discussed within the text of this research work.
机译：本研究提供了关于铀同位素对1-100meV射击能量范围对铀同位素对铀同位素反应的理论和实验结果中的横截面生产过程的现有证据，以提高核刺激的可靠性。在核反应堆中U-235的这种裂变反应中，将释放大量的能量作为能够满足全球能量需求而不会与其他来源相比的污染过程。这项工作的主要目的是通过描述，通过与从EXFOR获得的实验数据进行比较。 U-235（N，2N）U-234，U-235（N，3N）U-233，U-235（N，Gamma）U-236，U-235（N，F）的横截面值是使用计算机代码完成而获得，并由IAEA的EXFOR浏览相应的实验值。将理论结果与从EXFOR DATA BANK取得的实验数据进行比较。计算机代码完成已被用于使用相同的输入参数集的分析，并且通过电子表格和源-8软件的帮助绘制图形。源于实验数据和计算机代码计算的不确定性的量化在最终评估结果中起着重要作用。将计算出总横截面的结果与文献中的前进的实验数据进行比较，并且在实验和理论数据之间发现了良好的一致性。分析了计算数据的这种比较并用表格和图形描述解释，结果在本研究工作的文本内简要讨论。

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