شماره مدرك :
8847
شماره راهنما :
8208
پديد آورنده :
داتلي بگي، مائده
عنوان :

بهينه سازي طيف انرژي نوترون حاصل شكافت با طراحي يك مجموعه شكل دهنده طيف (BSA) به منظور استفاده در BNCT با استفاده از كد MCNPX

مقطع تحصيلي :
كارشناسي ارشد
گرايش تحصيلي :
فيزيك - هسته اي
محل تحصيل :
اصفهان: دانشگاه صنعتي اصفهان، دانشكده فيزيك
سال دفاع :
1392
صفحه شمار :
نه،105ص.: مصور،جدول،نمودار
يادداشت :
ص.ع.به فارسي و انگليسي
استاد راهنما :
محمدحسن علامت ساز
استاد مشاور :
ياسر كاسه ساز
توصيفگر ها :
نوترون تراپي , طيف شكافت حاصل از راكتور
تاريخ نمايه سازي :
20/2/93
استاد داور :
اكبر پروازيان، ظفرا... كلانتري
دانشكده :
فيزيك
كد ايرانداك :
ID8208
چكيده انگليسي :
Optimization of fission neutron spectrum by designinga beam shaping assembly BSA in order to be used inboron neutron capture therapy BNCT using MCNPX code Maede Datli Begi m datli@ph iut ac ir 9 11 2013 Department of Physics Isfahan University of Technology Isfahan 84156 83111 Iran Degree M Sc Language FarsiSupervisor Dr Alamatsaz alamatsa@cc iut ac irAbstractBoron Neutron Capture Therapy BNCT is an effective and acceptable therapeutic method forthe treatment of brain tumors This method based on 10 B n 7 Li reaction In this method stable isotope 10 B will be localized into the tumor after infusion into the patient Then thepatient is irradiated by a beam of epithermal neutrons The neutrons are changed into thermalneutrons through passing different tissues Absorption of thermal neutrons in the nuclei 10 Bwill lead to the production of particles and 7 Li The deposited energy from this reactiondistroies boron labeled tumor cells Two important factors are boron carrier drug and neutronsource Nuclear reactors are the best neutron source for BNCT In order to use these neutronsources for BNCT it is necessary to optimize energy intensity and contaminations by designinga Beam Shaping Assembly BSA The BSA consists of moderator reflector collimator andfilters In this research a BSA has been designed based on a nuclear reactor as neutron sourceusing MCNPX code Many parameters involve in designing a BSA including shape materialand thickness of the material their order and etc All these parameters can not be optimizedsimultaneously Therefore we have to optimize each parameter in a separate stage Each pa rameter will be optimized according to result of its previous stage The output neutron beamfrom the designed BSA have properties that determined by international atomic energy agency IAEA Final design of BSA can be used as a set for boron neutron capture therapy In orderto have a better analysis from this spectrum the defined criteria for phantom parameters includ ing ADDR AD TG and TT were evaluated All these parameters have a good condition fortreatment Dosimetry considerations show that fission neutron spectrum can be used in BNCT Keywords BNCT Fission neutron spectrum BSA phantom dosimetry
استاد راهنما :
محمدحسن علامت ساز
استاد مشاور :
ياسر كاسه ساز
استاد داور :
اكبر پروازيان، ظفرا... كلانتري
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