在本論文中我們利用中子活化分析方法，於清華水池式反應器硼中子捕獲治療設施進行相關研究與應用，內容主要分為三個部分：超熱中子射束品保量測、病人活化分析以及新型中子活化分析方法之建立。
中子射束之品質及穩定性對硼中子捕獲治療而言非常重要，藉由中子即時監測系統，可觀察照射時中子通率隨時間之變化，故此系統在硼中子捕獲治療臨床試驗中扮演非常重要的角色。為了確保中子即時監測系統運作情形良好，我們使用金鋁以及純銅箔片作為活化偵檢器，置於壓克力假體內進行中子照射，利用加馬能譜分析系統計測其活度，以定期執行品保量測。此部分研究將呈現自2010年首次硼中子捕獲治療臨床試驗以來，截至2017年3月之品保量測歷程及結果。
病人在接受硼中子捕獲治療照射後，將因活化而帶有放射性，因此病人活化分析是必要的。我們利用中子活化分析方法，對受到活化之病人進行放射性核種分析，由定性分析結果我們可得到放射性核種的種類，此外亦在一些假設條件下，對放射性核種進行定量分析，估算其活度。另一方面，我們也利用測量計進行加馬射線劑量率之量測，並與放射性核種之定性分析結果比對與探討。此部分研究將同樣呈現截至2017年3月為止，一共26位接受硼中子捕獲治療照射之病人的活化分析結果。
最後，本論文以中子活化分析方法為基礎，利用硼中子捕獲治療超熱中子射束作為中子源，提出一全新之改良型絕對校正法。我們將傳統絕對校正法中的單位靶核反應率計算方式進行改良，藉由已建立完善之中子射源項THOR-Y09，可利用蒙地卡羅模擬計算程式MCNPX來計算單位靶核反應率，同時搭配硼中子捕獲治療超熱中子射束即時監測系統，將中子通率隨時間的變化一併列入考慮。此部分研究將說明改良型絕對校正法之原理，並選用多種已知元素組成之待測樣品進行定性及定量分析，藉由實測結果展現此方法之分析能力。

In this work applications of neutron activation analysis (NAA) on boron neutron capture therapy (BNCT), including quality assurance (QA) measurement of epithermal neutron beam, patient activation analysis and a brand new method of neutron activation analysis, have been performed and studied.
The quality as well as stability of neutron beam is obviously crucial for BNCT. By utilizing a neutron online monitoring system, one can obtain the variations of neutron fluence rate against time and therefore, this system plays an important role during BNCT irradiation. To perform QA measurement, Au/Al and Cu foils were employed as an activation detector and were irradiated inside a PMMA phantom. By measuring the activities of these activation detectors, calibration factors can thus be achieved. In this section we demonstrated the results of QA measurement from the very first BNCT clinical trial in 2010 until March 2017.
Patients receiving BNCT irradiation become radioactive. By means of qualitative NAA, radioactive nuclides activated within patients were identified. The estimated activities of the corresponding radioactive nuclides were achieved based on several assumptions. Gamma-ray dose rate measurements utilizing a survey meter were also performed. In this section the results of neutron activation survey on up to date 26 patients following BNCT were demonstrated.
Finally, a modified absolute calibration method of NAA was proposed. Reaction rates per atom were calculated by using MCNPX Monte Carlo code with a well established neutron source. Time dependency of neutron fluence rate during the irradiation was achieved by utilizing a neutron online monitoring system. Different types of samples with given compositions were measured to test the adequacy and performance of this proposed modified absolute calibration method.

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