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  • 學位論文

以中子活化分析法評估醫用迴旋加速器室內的中子分佈情形

Evaluate Stray Neutron Distribution in Medical Cyclotron Vault Room by Neutron Activation Analysis Approach.

指導教授 : 陳健懿
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摘要


以中子活化分析法(Neutron Activation Analysis, NAA)評估中山醫 學大學附設醫院迴旋加速器室內中子(neutron)分佈情形,放射製藥生 產的過程中產生中子,例如:核醫在診斷時使用的18F, 11C, 13N , 15O, 當迴旋加速器運轉,我們以中子與銦片進行115In(nf,n’)115mIn 及115In (nth,γ)116m1In 核反應,分別來評估快中子與熱中子的通率(flux)。將銦 片經稱重、密封、佈點於迴旋加速器室內的62 個位置,另外每片銦 片需在迴旋加速器的運轉中,被照射超過80 分鐘,再使用高純度鍺 型偵檢器(HPGe)量測加馬射線去解算快中子和熱中子的通率。本論文 發現快中子和熱中子的通率由小至大分別為(3.47±0.11)×103 至 (1.06±0.21)×104 n⋅cm-2/s,9 至965n⋅cm-2/s。在此,包含的中子的最小 可測值(Minimum Detectable Limit, MDL),說明了本方法的可適性。 相對應地,在測量62 點中快中子和熱中子強度相關的信賴區間 (confidence level)分別達到95%。而若能圖譜裡的高能康普吞散射或 較低強度γ 射線波峰,會導致熱中子通率可以量測的比率降低。

並列摘要


Stray neutron distribution in a medical cyclotron vault room was evaluated by neutron activation analysis (NAA). Neutrons were generated in the production of radioactive nuclides, such as 18F, 11C, 13N and 15O, for diagnostic usage. Indium foil was adopted to evaluate the stray fast and thermal neutron intensity based on 115In(nf, n’)115mIn and 115In(nth, γ)116m1In reaction, respectively. The indium foils were weighed sealed and placed at 62 points around the 6.7×8.2 m2 cyclotron room. Additionally, each indium foil was exposed for over 80 minutes during cyclotron operation and γ-peaks were analyzed using an HPGe detector to evaluate the number of stray fast (Φf) or thermal (Φth) neutrons. The minimum to maximum numbers of fast and thermal neutrons were (3.47±0.11)×103 to (1.06±0.21)×104 n⋅cm-2⋅sec-1 and 9 to 965 n⋅cm-2⋅sec-1, respectively. The minimum detectable limit for stray neutrons was included herein to demonstrate the reliability. Accordingly, 60 and two points, respectively, the confidence level associated with the reported intensities of fast and thermal neutrons reached 95%. The low qualified ratio in the evaluation of stray thermal neutrons might have been caused by either the high Compton scattering plateau or the low intensity of the gamma-ray peak in the relevant spectrum.

參考文獻


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