回旋加速器
质子
蒙特卡罗方法
核数据
物理
产量(工程)
核物理学
梁(结构)
材料科学
中子
数学
光学
统计
热力学
等离子体
作者
Tianquan Wang,Zhang Hu,Jiuhui Zhang,Ruimin Wang,Xiaofei Zhang,Yongzhi Yin,Wei Fan
标识
DOI:10.1088/1748-0221/18/09/p09029
摘要
Abstract Cooper-64 ( 64 Cu) has good potential for use in the diagnosis and treatment of tumors. It can be produced by irradiating an enriched 64 Ni target with a small proton cyclotron system. Based on the demand for 64 Cu, a suitable production plan can be developed. Due to the high cost of 64 Ni, it is important to simulate the production process in order to find a cost-effective method for producing 64 Cu. In this work, Geant4 software was used in conjunction with the Evaluated Nuclear Data File (ENDF/B-VII.1) and the TALYS-based Evaluated Nuclear Data Library (TENDL-2019) to calculate the 64 Ni(p,n) 64 Cu reaction cross section. The TRIM code was then used to calculate the proton projection range in the 64 Ni target. Finally, the saturation yield of 64 Cu was obtained for proton energies between 2 MeV and 20 MeV and target thicknesses ranging from 0.1 mm to 1 mm.
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