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ESTIMATION OF THERMAL & EPITHERMAL NEUTRON FLUX AND GAMMA DOSE DISTRIBUTION IN A MEDICAL CYCLOTRON FACILITY FOR RADIATION PROTECTION PURPOSES USING GOLD FOILS AND GATE 9
Radiation Protection Dosimetry ( IF 0.8 ) Pub Date : 2021-02-18 , DOI: 10.1093/rpd/ncab034
Fouad A Abolaban 1, 2 , Mohammed A Alawi 1 , Eslam M Taha 1, 2 , Ezzat Elmoujarkach 1, 3 , Essam M Banoqitah 1 , Abdulsalam M Alhawsawi 1, 2, 4 , Paolo De Maio 5 , Gaetano Lopopolo 5 , Anna Tolomeo 5 , Vincenzo Dimiccoli 5 , Andrew Nisbet 6
Affiliation  

The aim of this study is to characterise the neutron flux generated directly behind targets used in medical cyclotrons. The characterisation process aims at determining the feasibility of using the generated neutrons for research purposes in neutron activation analysis. The study was performed by activating gold foils placed directly behind the cyclotron targets. The thermal and epithermal neutron flux were found to be 4.5E+05 ± 8.78E+04 neutrons cm−2 s−1 and 2.13E+06 ± 8.59E+04 neutrons cm−2 s−1, respectively. The flux value is the same order of magnitude listed in the manual produced by the cyclotron manufacturer. The results are encouraging and show high potential for using the cyclotron facility as a thermal neutron source for research purposes. However, it is important radiation protection procedures be followed to ensure the safety of researchers due to the high gamma dose rate measured directly behind the target at 2.46 Sv/h using an OSL chip during the beam on time.

中文翻译:

使用金箔和门 9 估计医疗回旋加速器设施中热和外热中子通量和伽马剂量分布的辐射防护目的

本研究的目的是描述直接在医用回旋加速器中使用的目标后面产生的中子通量。表征过程旨在确定在中子活化分析中使用产生的中子用于研究目的的可行性。该研究是通过激活直接放置在回旋加速器目标后面的金箔来进行的。发现热和超热中子通量分别为 4.5E+05 ± 8.78E+04 个中子 cm-2 s-1 和 2.13E+06 ± 8.59E+04 个中子 cm-2 s-1。通量值与回旋加速器制造商生产的手册中列出的数量级相同。结果令人鼓舞,并显示出将回旋加速器设施用作研究目的的热中子源的巨大潜力。然而,
更新日期:2021-02-18
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