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研究能级密度参数对聚变结构材料钛、铜和锆的(p,n)和(p,2n)反应截面的影响。

Investigation of level density parameter effects on (p,n) and (p,2n) reaction cross-sections for the fusion structural materials Ti, Cu and Zr.

作者信息

Özdoğan H, Şekerci M, Sarpün I H, Kaplan A

机构信息

Akdeniz University, Biophysics Department, Antalya, Turkey.

Süleyman Demirel University, Physics Dept., Isparta, Turkey.

出版信息

Appl Radiat Isot. 2018 Oct;140:29-34. doi: 10.1016/j.apradiso.2018.06.013. Epub 2018 Jun 15.

DOI:10.1016/j.apradiso.2018.06.013
PMID:29936273
Abstract

The materials used in fusion reactor must be resistance to the harmful effects of radiation in the manner of material itself. Selection of the appropriate materials used in nuclear reactor has a crucial importance to achieve the maximum efficiency and security. Ti, Cu and Zr are known to be employed as first wall materials in fusion reactors. In this study, level density parameter effects on (p,n) and (p,2n) reaction cross-section calculations have been investigated by employing different level density models within TALYS 1.8 computer code for Ti, Cu and Zr selected as target materials. Also, for these isotopes (p,n) and (p,2n) reaction cross-section calculations have been done by using two different level density models of EMPIRE 3.2 code. For calculations; Constant Temperature Fermi Gas Model, Back Shifted Fermi Gas Model, Generalised Super Fluid Model and Microscopic level densities (temperature dependent Hartree Fock Bogolyubov, Gogny Force) from Hilaire's combinatorial tables have been used from TALYS 1.8. In addition, Generalised Superfluid Model and Hartree Fock Bogolyubov Model have been selected for calculations from EMPIRE 3.2 code. To appoint the best level density model, the relative variance analyses have been done. The cross-section calculations have been repeated via TALYS 1.8 level density models by changing the a parameter replacing with the obtained one from the best level density model result and value taken from the literature for each isotope. To analyze and comment about the outcomes of the study, a comparison of the results have been done with each other and the experimental data taken from the literature.

摘要

聚变反应堆中使用的材料必须以材料自身的方式抵抗辐射的有害影响。选择核反应堆中使用的合适材料对于实现最高效率和安全性至关重要。已知钛、铜和锆被用作聚变反应堆的第一壁材料。在本研究中,通过在TALYS 1.8计算机代码中使用不同的能级密度模型,对选为靶材料的钛、铜和锆,研究了能级密度参数对(p,n)和(p,2n)反应截面计算的影响。此外,对于这些同位素,使用EMPIRE 3.2代码的两种不同能级密度模型进行了(p,n)和(p,2n)反应截面计算。为了进行计算;从TALYS 1.8中使用了恒温费米气体模型、后移费米气体模型、广义超流体模型以及来自希莱尔组合表的微观能级密度(温度相关的哈特里-福克-博戈柳博夫、戈尼力)。此外,从EMPIRE 3.2代码中选择了广义超流体模型和哈特里-福克-博戈柳博夫模型进行计算。为了确定最佳能级密度模型,进行了相对方差分析。通过用从最佳能级密度模型结果中获得的参数替换a参数,并为每个同位素采用文献中的值,通过TALYS 1.8能级密度模型重复了截面计算。为了分析和评论该研究的结果,将结果相互进行了比较,并与文献中的实验数据进行了比较。

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