6532

6097

كارشناسي ارشد

فيزيك هسته اي

اصفهان: دانشگاه صنعتي اصفهان، دانشكده فيزيك

1390

يازده، 87ص.: مصور، جدول، نمودار

ص.ع. به فارسي و انگليسي

ظفرا... كلانتري

احمد شيراني

17/12/90

محمد حسن علامت ساز

1396/10/12

كتابنامه

فيزيك

فيزيك

ID6097

به فارسي و انگليسي: قابل رويت در نسخه ديجيتالي

Designing a Beam Shaping Assembly BSA for Isfahan Miniature Neutron Source Reactor MNSR for Boron Neutron Capture Therapy BNCT Hajar Tavakoli h tavakoli@ph iut ac ir Date of Submission September Department of Physics Isfahan University of Technology Isfahan Iran Degree M Sc Language Persian Supervisor Seyed Zafarollah kalantari zafar@cc iut ac irAbstract Boron Neutron Capture Therapy BNCT is one of the efficient method to treat some cancer tumors particularly the brain tumors glioblastoma multiform In this treatment boron with particular chemicalcompound is concentrated within the tumor Then a high intensity beam of epithermal neutrons is focused onthe tumor area on the head Thermal neutron in the reaction B n Li produces energetic alpha and lithiumparticles with a range about the size of the cells These charged particles deposit their kinetic energies to thecell which leads to destroy the cancer cell For boron neutron capture therapy we need a high flux of thermal neutrons at the place of tumor becausethe cross section of the B n Li reaction has a high value for thermal neutrons Before neutrons reach thetumor they should go through the skin skull and brain tissues Most of thermal neutrons in the beam arecaptured by the normal cells So they can produce damages The epithermal neutrons slow down by elastic orinelastic collisions Therefore thermal neutrons should be removed and fast neutrons should be moderated toconvert epithermal neutrons On the other hand the rays from inelastic collisions should be shielded toprotect their damages on the normal cells Therefore neutron beam to use in BNCT should have somecharacteristics epi n cm s Dnf epi Gycm D epi Gycm epi th j For thispurpose a Beam Shaping Assembly BSA should be designed Designing a beam shaping assembly related tothe kind of neutron source To design a BSA many parameters should be determined kind of materials shapeand dimentions of materials Usually Li is used for capturing the thermal neutrons AlF is used as moderatorof the fast neutrons Bi is used for filtering the rays and Pb is used as reflector and collimator of neutrons One of the high intensity neutron source in Isfahan is Miniature Neutron Source Reactor MNSR Thisreactor is a pool tank type reactor with power of kW highly enriched uranium fuel natural watermoderator and metal beryllium reflector Its neutron flux is in order of n cm s We havesimulated the neutron transport from the core of the reactor to the output windows of BSA for differentdesign of BSA For this purpose we have used the MCNP C code which is a suitable Monte Carlo code tosimulate the neutron interactions in different materials and geometries Our calculations show that the neutron flux of the MNSR reactor can be used for BNCT and we havepresented a design of a BSA to produce optimum neutron beam with required characteristics for BNCT Keywords Neutron therapy BNCT MNSR Monte Carlo method

ظفرا... كلانتري

احمد شيراني

محمد حسن علامت ساز