Please use this identifier to cite or link to this item:
https://repository.sustech.edu/handle/123456789/21108| Title: | Monte Carlo Modeling of Fast Neutron Moderating System Suitable For Use in Boron Neutron Capture Therapy |
| Other Titles: | محاكاة مونتي كارلو لنمذجة نظام لتهدئة النيوترونات السريعة المستخدمة في تقنية إلتقاط البورون نيوترون العلاجية |
| Authors: | Abakar, TahaniAbakar Mohamed Supervisor, -Nassreldeen Abdelrazig Abdelbar iElsheikh Co-Supervisor, -AhamedElhassanElfaki |
| Keywords: | science Physics Monte Carlo Modeling Fast Neutron Moderating System Suitable Boron Neutron Capture Therapy |
| Issue Date: | 22-Nov-2017 |
| Publisher: | Sudan University of Science and Technology |
| Citation: | Abakar, TahaniAbakar Mohamed . Monte Carlo Modeling of Fast Neutron Moderating System Suitable For Use in Boron Neutron Capture Therapy \ TahaniAbakar Mohamed Abakar ; NassreldeenAbdelrazigAbdelbariElsheikh .- Khartoum: Sudan University of Science and Technology, college of Science, 2017 .- 63p. :ill. ;28cm .- M.Sc |
| Abstract: | There is no one treatment for cancer and the search for ways to combat cancer have led to many different treatments, including surgery, chemotherapy, and radiation therapy. However, these treatments are not always effective, and in such cases new treatments must be developed. Boron neutron capture therapy (BNCT) is a treatment that has been proposed to combat brain tumor and Neck tumors, two tumors that are resistant to traditional cancer therapies. Boron neutron capture therapy (BNCT) is based on the nuclear reaction that occurs when boron-I0 is irradiated with low-energy thermal neutrons to yield alpha particles and recoiling lithium- 7 nuclei ( B10+nth-->[B 11]--> He42+Li7+2.31 MeV ). The potential of the spontaneously fissioning isotope 252Cf, to provide epithermal neutrons for use in boron neutron capture therapy (BNCT) has been investigated using Monte Carlo simulations to design an assembly composed of located inside a gamma filter made of sphere of high density lead, 1cm inner radius and 3 cm outer radius, which in turn located inside a fast neutron moderator in a form of a cylinder of radius 13cm, the moderator is surrounded by the outer radius is 15cm and the space between the two cylinders is filled with graphite for reflection. A third cylinder is added with a diameter of 17cm and filled with borated material to work as staff shielding. The height of the containing outer cylinder is 80cm the pump was designed and tested and the neutron flux was found 3.4×109 n / cm2.s this result is in excellent coherence compared to the result of previous studies this is due to optimal selection of materials according to the required standards as explained by the simulation in chapter four. |
| Description: | Thesis |
| URI: | http://repository.sustech.edu/handle/123456789/21108 |
| Appears in Collections: | Masters Dissertations : Science |
Files in This Item:
| File | Description | Size | Format | |
|---|---|---|---|---|
| Monte Carlo Modeling ... .pdf | Research | 908.14 kB | Adobe PDF | View/Open |
Items in DSpace are protected by copyright, with all rights reserved, unless otherwise indicated.