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研究生:何任展
研究生(外文):Ren-Jhan He
論文名稱:MegaShield軟體模擬近接治療之空腔劑量分佈
論文名稱(外文):The Study of Cavity Dose Distribution for MegaShield Software Simulated of Afterloading Brachytherapy
指導教授:林招膨林招膨引用關係
指導教授(外文):Jao-Perng Lin
學位類別:碩士
校院名稱:元培科技大學
系所名稱:醫學影像暨放射技術研究所
學門:醫藥衛生學門
學類:醫學技術及檢驗學類
論文種類:學術論文
畢業學年度:101
語文別:中文
論文頁數:56
中文關鍵詞:MegaShield點核仁法近接治療距離平方反比
外文關鍵詞:MegaShieldPoint Kernel MethodBrachytherapyInverse Square Law
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放射治療之目的為給予腫瘤組織正確劑量,增加腫瘤控制率,降低正常組織副作用併發率。使用高劑量率近接治療(high dose rate brachytherapy, HDR)病患,於劑量給予上存在著多項影響因素,包含電腦斷層影像系統、治療計畫運算系統(treatment planning system, TPS)、射源校正誤差及停留位置與時間是否正確等,同時劑量梯度變化大、單次給予劑量高,故選擇適合量測近接治療劑量之驗證系統為一項重要議題。
本研究是利用MegaShieldTM 3.0程式模擬後荷式近接治療(Afterloading Brachytherapy)192Ir核種治療之空腔劑量分佈,結果與將兩核種之劑量分佈結果做比較。MegaShield軟體是為利用點核仁法作為屏蔽計算的一套計算軟體。程式內建多種射源幾何、材質及屏蔽結構可供選擇,且屏蔽層數無限制。再利用點射源分別計算的方式,先求出每顆射源對偵測點的劑量貢獻,在將各射源劑量做積分相加,求出偵測點的實際劑量,並討論修正組織不均勻性。
本文利用空腔、時間、射源強度、射源大小及形狀,來建立一套可以更精準計算其空腔劑量之分佈的公式。用點射源求取距離平方反比(1/r2)、射源活度(A)及時間(t)來做線狀射源尺寸大小積分並做其加總,把其數據併入空腔去做評估(不考慮回散射因素)。
本方法計算空腔劑量有其準確性,這對於推算輻射鋼筋檢測及近接治療之治療室的空腔劑量的量測有更大的幫助。對不同空腔介質的劑量分佈或考慮回散射因素,亦可提供修正的計算方法。

In this paper, we use point source to count the inverse square law (1/r2), radiation source activity and time, to calculate the sum integral of the linear radiation source size, and it’s to apply the data into the space for assessment, without considering backscatter factor.
This method for calculate of the space dose is accurate, and it is helpful to calculate the detection of radiation steel bar radiation dose of body in brachytherapy takes by the cavity dose of therapy room. The dose distribution of the different cavity dose or backscatter factors, it can provide a amend calculation method.
This study is the using MegaShieldTM 3.0 program simulation brachytherapy treatment (Afterloading Brachytherapy) 192Ir and 60Co nuclide therapy spatial dose distribution, and then two nuclides dose distribution results for comparison.
MegaShield software for the use of point of the nucleolus law as shielding calculation of a set of computing software. The program built-in a variety of radiation source geometry, material and shielding structures to choose from, and shielding layers unlimited. Point source were calculated, first calculate the dose contribution of every single source moving the detection point in the dose of the radiation source to the integral sum, and calculate the actual dose of the detection point, and discuss amendments to uneven sex.

中文摘要 ………………………………………………………………. I
英文摘要 ……………………………………………………………... III
致 謝 ……………………………………………………………... IV
目 錄 ……………………………………………………………... V
表 目 錄 ……………………………………………………………... VI
圖 目 錄 …………………………………………………………….. VII
第一章 緒論
1.1 前言……………………………………………………….1
1.2 研究背景………………………………………………….4
1.3 研究目的………………………………………………….5
第二章 基礎理論
2.1輻射與物質之相互作用 ………………………………… 6
2.1.1光子與物質之作用機制……………………….… 6
2.1.2電子與物質之作用機制……………………….… 7
2.1.3能量轉移係數和能量吸收係數………………......8
2.2近接治療介紹及劑量學簡介..……………………….........9
2.2.1 近接治療類型………………………..……………9
2.2.2 近接治療臨床應用………………………………11
2.2.3 各種射源之比較…………………………………13
2.2.4 近接治療限制……………………………………20
2.2.5管腔及不同射源在近接治療之比較…………….21
第三章 研究設備與方法
3.1 MegaShield軟體…………………………………………… 28
3.1.1 MegaShield軟體之簡介………..……………….. 28
3.1.2 MegaShield軟體之應用……….……………….. .29
3.1.3 MegaShield參數設定………….……………….. 31
3.2 蒙地卡羅軟體.………………………………………….. 34
3.2.1蒙地卡羅模擬程式……………………………… 34
3.2.2蒙地卡羅基本原理……………………… ………34
3.3模擬假體設計……………….…………………………… 39
3.4近接治療劑量公式……………………………………….40
第四章 結果與討論
4.1 MegaShield模擬結果…………….……………………… 42
4.2蒙地卡羅模擬結果……………….……………………… 43
第五章 結論
參考文獻…………………………………………………..…. 54

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2. Ruder Boskovic Institute,Department of Technology,Nuclear Energy and Radiation Protection,”Point kernel calculatin of dose fields from line sources using expanded polynomial from of buildup factor data: Generalized secant integral-series pepresentation”,IVAN MICHIELI,1998,51,121-128.
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