Influence of level density models on proton and deuteron-induced reactions using zinc target for the production of 66-68Ga medical radioisotopes

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Bassam T. Al-Azraq , Raghad I. Mahmood , Lubna Abduljabbar Mahmood , Radhwan Ch. Mohsin , Rusul S. Jaffer
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Abstract

Due to their medical importance in imaging and therapy, this paper examines proton- and deuteron-induced reactions on zinc targets from a theoretical perspective. Medically important 66Ga, 67Ga, and 68Ga were simulated using TALYS 2.0 and different level density models. The relative variance technique was used to assess model agreement with experimental data given in EXFOR library. Key production parameters, including radionuclidic impurities, optimal energy range, theoretical yield, and target thickness, were derived from the selected theoretical model, which was chosen based on its agreement with experimental trends. Results confirmed the models’ predictive accuracy across a wide energy range in estimating the nuclear reaction cross-sections for 66,67,68Ga production. For a number of studied reactions, the TGHFB model specifically agreed very well with the experimental data. Zinc targets proved effective and feasible for producing 66,67,68Ga at low proton and deuteron energies, as typically available in medical cyclotrons.
能级密度模型对用锌靶生产66-68Ga医用放射性同位素的质子和氘核诱导反应的影响
由于它们在医学成像和治疗中的重要性,本文从理论角度探讨了锌靶上质子和氘核诱导的反应。使用TALYS 2.0和不同级别密度模型模拟医学上重要的66Ga、67Ga和68Ga。采用相对方差法评估模型与EXFOR库中实验数据的一致性。关键生产参数包括放射性核素杂质、最优能量范围、理论产率和目标厚度,从所选择的理论模型中得出,并根据其与实验趋势的一致性进行选择。结果证实了该模型在估计66,67,68ga生产的核反应截面时在宽能量范围内的预测准确性。对于许多已研究的反应,TGHFB模型与实验数据特别吻合。锌靶被证明是有效和可行的,可以在低质子和氘核能量下产生66、67、68Ga,如通常在医疗回旋加速器中使用。
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来源期刊
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
期刊介绍: Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
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