簡易檢索 / 詳目顯示

研究生: 張志豪
Chih-Hao Chang
論文名稱: 清華水池式反應器硼中子捕獲治療射束中子通率測量
The Measurement of Neutron Fluence Rate for Tsing Hua Open-pool Reactor Boron Neutron Capture Therapy Beam
指導教授: 江祥輝
Shiang-Huei Jiang
口試委員:
學位類別: 碩士
Master
系所名稱: 原子科學院 - 工程與系統科學系
Department of Engineering and System Science
論文出版年: 2006
畢業學年度: 94
語文別: 中文
論文頁數: 111
中文關鍵詞: 硼中子捕獲治療中子活化偵檢器中子活化分析技術中子通率測量
相關次數: 點閱:3下載:0
分享至:
查詢本校圖書館目錄 查詢臺灣博碩士論文知識加值系統 勘誤回報
  • 硼中子捕獲治療(BNCT)應用在癌症治療,尤其是惡性腦腫瘤及黑色素瘤,能達到治療效果並降低對正常細胞的傷害,成果較傳統的放射性治療要來的好。目前BNCT的發展主要是以超熱中子束來進行治療,在進入人體後減速形成熱中子,並在2到3公分處產生尖峰,一方面能夠有效治療深層的腫瘤,一方面能夠避免外科手術打開頭蓋骨的危險性。

    本研究為清華水池式反應器(THOR)改建的BNCT超熱中子射束特性研究的一部份,利用活化偵檢器進行THOR BNCT射束的中子通率測量。活化偵檢器為金鋁、純銅、錳鎳三種金屬箔片構成的箔片組,箔片活化後利用中子活化分析技術(高純鍺偵檢器進行加馬射線能譜計測,GammaVision軟體進行能譜分析)計算出箔片反應率,並利用箔片反應率推算出熱中子以及超熱中子通率值。

    實驗目的主要在建立中子通率測量的標準程序,反應器1 MW功率運轉下,測量空氣中射束出口位置的熱中子通率、超熱中子通率;以及沿射束中心軸線距射束出口16公分位置,一個35 × 35 × 31立方公分水假體內,隨深度變化各點位置的熱中子及超熱中子通率值測量。並配合蒙地卡羅方法採用MCNP4C 程式及ENDF/B-VI反應截面資料,進行空氣中、水假體內,箔片反應率及中子通率的模擬計算結果。利用實驗測量結果與模擬計算結果相比對,並試圖解釋其中差異的存在以及誤差的可能性。

    活化偵檢器中子通率測量屬於射束特性標準測量,測得的中子通率將應用在分裂腔的校正及游離腔、熱發光劑量計測量的參照標準。


    目錄 摘要……………………………………………………i 誌謝……………………………………………………ii 目錄……………………………………………………iii 表目錄…………………………………………………vii 圖目錄…………………………………………………x 第一章 緒論………………………………………1 第二章 中子活化分析……………………………3 第三章 活化偵檢器原理…………………………15 第四章 實驗設備與流程…………………………23 第五章 實驗結果與分析…………………………49 第六章 模擬計算比對……………………………64 第七章 結論與建議………………………………80 參考文獻………………………………………………86 附錄……………………………………………………89

    參考文獻

    [1] IAEA, Current Status of Neutron Capture Therapy, IAEA-TECDOC-1223, Vienna, 2001
    [2] G.L. Locher, Biological Effects and Therapeutic Possibilities of Neutrons, Am. J. Roentgenol. Radium Ther. Nul. Med., 36: 1-13, 1936.
    [3] A.H. Soloway, H. Hatanaka, M.A. Davis, Penetration of Brain and Brain Tumor. VII. Tumor-binding Sulfhydryl Boron Compounds, Journal of Medicinal Chermistry, 10: 714-717, 1967.
    [4] H. Hatanaka and Y. Nakagawa, Clinical results of long-surviving brain tumor patients who underwent boron neutron capture therapy, International Journal Radiation Oncology Biology Physics, 28(5): 1061-6, 1994
    [5] H. Hatanaka, et al., Clinical Experience of Boron Neutron Capture Therapy for Gliomas - A Comparison with Conventional Chemo-Immuno-Radiotherapy., H. Hatanaka (ed.) Boron Neutron Capture Therapy for Tumors, Niigata, Japan: Nishimura Co., Ltd., 1986
    [6] S. Berg and W.N. McElroy, A Computer Automated Iterative Method for Neutron Flux Spectra Determination by Foil Activation, Atomics International Report AFWL-TR67-41, 1967
    [7] 牛效中,利用活化中子偵檢器測量清華水池式反應器之中子能譜,碩士論文,國立清華大學原子核工程研究所,1982
    [8] 趙旋爾,中子照射及活化分析,國興出版社,1991
    [9] 郭正典,中子活化分析及其應用,科儀新知,第22卷第3期,頁6-14,2000
    [10] G.F. Knoll, Radiation Detection and Measurement, 3rd ed. New York: John Wiley & Sons Inc., P.744-746, 2000
    [11] J.R. Lamarsh and A.J. Baratta, Introduction to Nuclear Engineering, 3rd ed. New Jersey: Prentice Hall, P.37-74, 2001
    [12] IAEA, Neutron Fluence Measurement, Technical Reports Series No.107, Vienna, 1970
    [13] ASTM, E 262-03, Standard Test Method for Determining Thermal Neutron Reaction and Fluence Rates by Radioactivation Techniques, 2003
    [14] ASTM, E 261-03, Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques, 2003
    [15] ASTM, E 944-02, Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, 2002
    [16] O. Shcherbakov and H. Harada, Resonance Self-shielding Corrections for Activation Cross Section Measurements, Journal of Nuclear Science and Technology, Vol.39, No.5, P.548-553, 2002
    [17] E. Martinho and J. Salgado and I.F. Gonçalves, Universal Curve of the Thermal Neutron Self-shielding Factor in Foils, Wires, Spheres and Cylinders, Journal of Radioanalytical and Nuclear Chemistry, Vol.261, No.3, P.637-643, 2004
    [18] E. Martinho and I.F. Gonçalves and J. Salgado, Universal Curve of Epithermal Neutron Resonance Self-shielding Factors in Foils, Wires and Spheres, Applied Radiation and Isotopes, 58: P.371-375, 2003
    [19] J. Salgado and I.F. Gonçalves and E. Martinho, Epithermal Neutron Self- shielding Factors in Foils for Collimated Beams, Applied Radiation and Isotopes, 60: P.677-681, 2004
    [20] I.F. Gonçalves and E. Martinho and J. Salgado, Monte Carlo Calculation of Epithermal Neutron Resonance Self-shielding Factors in Foils of Different Materials, Applied Radiation and Isotopes, 56: P.945-951, 2002
    [21] W.P. Voorbraak, NRG 2003, Recommendations for the Dosimetry of Boron Neutron Capture Therapy, Petten, 21425/03.55339/C, 2003
    [22] 行政院國家科學委員會補助專題研究計畫成果報告,國立清華大學水池式反應爐改建為硼中子捕獲治療(BNCT)專用核反應爐研究計畫 子計畫一:反應 爐改建工程,2002
    [23] G.F. Knoll, Radiation Detection and Measurement, 3rd ed. New York: John Wiley & Sons Inc., P.405-454, 2000
    [24] EG&G ORTEC GMX-15185 High-Purity Germanium Coaxial Detector System Quality Assurance Data Sheet, 1995
    [25] EG&G ORTEC DSPEC TM Digital Gamma-Ray Spectrometer Hardware Manual, 1995
    [26] EG&E ORTEC Part No.774780, GammaVision R-32 (A66-B32 Software User’s Manual)
    [27] S.H. Jiang, J.H. Liang, J.T. Chou, U.T. Lin, W.W. Yeh, A Hybrid Method for Calculating Absolute Peak Efficiency of Germanium Detectors, Nuclear Instruments and Methods in Physics Research A 413: 281-292, 1998

    [28] R.D. Rogus, O.K. Harling, J.C. Yanch, Mixed Field Dosimetry of Epithermal Neutron Beams for Boron Neutron Capture Therapy at the MITR-II Research Reactor, Med. Phys. 21(10), 1994
    [29] J.F. Briesmeister (Ed.), MCNP-A General Monte Carlo N-Particle Transport Code, Version 4C, LA-13709-M, Los Alamos National Laboratory, Los Alamos, New Mexico, 2000
    [30] Y.-W. H. Liu, T.T. Huang, S.H. Jiang and H.M. Liu, Renovation of Epithermal Neutron Beam for BNCT at THOR, Applied Radiation and Isotopes 61, 1039 -1043, 2004
    [31] Y.H. Liu, S.H. Jiang, Y.-W. H. Liu, H.M. Liu, On-line Neutron Monitoring System of Epithermal Neutron Beam for BNCT at THOR, 12th International Congress on Neutron Capture Therapy, Takamatsu, Kagawa, Japan, Oct. 9-13, 2006
    [32] C.H. Chang, Y.H. Liu, A.Y. Chen, S.H. Jiang, Y.-W. H. Liu, H.M. Liu, A Study of Neutron Fluence Rates of the BNCT Beam at THOR Using Foil Activation, 12th International Congress on Neutron Capture Therapy, Takamatsu, Kagawa, Japan, Oct. 9-13, 2006

    無法下載圖示 全文公開日期 本全文未授權公開 (校內網路)
    全文公開日期 本全文未授權公開 (校外網路)
    全文公開日期 本全文未授權公開 (國家圖書館:臺灣博碩士論文系統)
    QR CODE