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研究生:李瑞萍
研究生(外文):Jui-Ping
論文名稱:醫用迴旋加速器中子輻射之度量
論文名稱(外文):Measurement of neutron radiation in self-shielded medical cyclotron
指導教授:周芬碧周芬碧引用關係陳健懿
指導教授(外文):Fen-Pi ChouChien-Yi Chen
學位類別:碩士
校院名稱:中山醫學大學
系所名稱:生化暨生物科技研究所
學門:生命科學學門
學類:生物科技學類
論文種類:學術論文
論文出版年:2007
畢業學年度:95
語文別:中文
論文頁數:78
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近年來因正子造影(Positron Emission Tomography,PET)檢查方式普及,各大醫院紛紛設立PET中心,且隨著醫用迴旋加速器(cyclotron)的設立,工作人員亦增加。迴旋加速器運轉過程中18O(p,n)18F核反應會產生額外中子,中子更會直接或間接造成工作人員及民眾的體外輻射劑量。本論文以(1)德國FAG公司出產之 FHT 751中子偵檢器度量中子劑量率,及(2)活化箔片法測量中子通率對設立於中山醫學大學附醫具自體屏蔽RDS-111迴旋加速器。結果發現,在加速器自體屏蔽接縫地面處得到的中子劑量率及中子通率均最高,並隨著距離的增加而減少,中子劑量率最高由接縫處191±0.15μSv/h降至門口2.48±0.01μSv/h,熱中子通率最高由接縫處地面上的2057±3.80 n/cm2 s1降至門口9.23±1.45 n/cm2 s1,這表示在迴旋加速器地面上的屏蔽較弱。為配合衛生署規定自民國九十五年一月一日實施「斷層掃描用正子放射同位素調製作業要點」,本中心於民國九十四年七月進行改建。加建短迷宮牆後,加速器室之中子通率降了1.52~4.02倍。研究結果顯示本加速器之自體屏蔽可有效阻擋由靶位釋出之中子,對人員造成的輻射劑量也相當低,而位於控制台等工作人員運轉時所在之處,測得之中子劑量率所造成體外輻射劑量更遠低於法規限值。由本研究可得知,在中山醫學大學附設醫院迴旋加速器中心工作,是相當安全的。

Accelerated growth in the use of positron emission tomography (PET) had been resulted in a steady increase in the number of PET centers in Taiwan. The neutrons that were emitted from (p, n) reactions directly or indirectly caused hazard to the health of medical personnel and the public. In this work, (1) FHT-751 neutron detector made by FAG was to monitor the neutron dose rate during the operating period; (2) neutron flux of cyclotron room was mapped using foil activation method at self-shielded RDS-111 cyclotron of Chung Shan Medical University Hospital (CSMUH). Results indicated that neutron dose rate and neutron flux were the highest one on the floor of the interlocking block, (191±0.15μSv h-1, 2057±3.80 n cm-2 s-1) and were reduced down to the door. (2.48±0.01μSv h-1, 9.23±1.45 n cm-2 s-1) The neutron dose rate decreased as the distance from the block increased, that clearly indicated the weakness of the self-shielded design of the lower part of the RDS-111 cyclotron. To meet the Guideline of production of PET published by Department of Health, the new design of self-shield CTI RDS-111 was improved by adding maze and wall. The neutron fluxes presented reducing factors of 1.52~4.02 due to this design. Annual “extra” neutron DR for medical personnel was measured and evaluated far below the recommended ICRP 60 limit. The results revealed that the shell-shielded system adequately protected well the laboratory personnel. Thus the medical professional staff and the general public in CSMUH were safe.

目 錄
中文摘要 Ⅰ
英文摘要 Ⅱ
誌 謝 Ⅲ
目 錄 Ⅳ
圖 目 錄 Ⅵ
表 目 錄 Ⅶ

第 一 章 緒 論 1
1.1 前言 1
1.2 文獻回顧 4
1.2.1迴旋加速器之中子通率與劑量 4
1.2.2中子測量偵檢儀具 7
1.3研究的目的 9
1.4迴旋加速器 10

第 二 章 量測的方法與儀具 20
2.1以 FHT 751 BIOREM中子偵檢器量測中子劑量率 20
2.2以活化箔片法測中子通率 26

第 三 章 結果 37
3.1本中心各地點中子劑量率背景值測量 37
3.2本中心運轉時中子劑量率 37
3.3運轉時人員工作環境之中子劑量率 43
3.4迴旋加速器室內中子通率之分佈 47
第 四 章 討論 52
第 五 章 結論 56
參考資料 58
附表一 測量點之座標 61
附表二 校正數值 62
附表三 迴旋加速器中心運轉時各點中子劑量率 68
附表四 銦片測量結果 70
附表五 位置相同測量高度不同之熱中子通率 76
專有名詞中英對照 77


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