Development of a Software for Rreconstruction of Neutron spectrum

, M.Sc. Thesis Sharif University of Technology Yousefnejad, Sirous (Author) ; Vossoughi, Naser (Supervisor) ; Etaati, Gholamreza (Co-Advisor)

Abstract

Dealing with natural and handmade radioactive materials and sources is of major aspects of nuclear science and technology. Useful applications of these materials and sources in different fields, such as energy production and health physics, caused the necessity of developing the detection and radiation protection methods. Each of these methods uses different equipment and approaches which are based on different kinds of radiations and radioactive sources. Despite the given ability of radiation detection, in some cases, recognition, distinguish, and estimation of a source radiation level is impossible due to bad effects of these equipment on measured spectrum. Detection of neutron spectrum in...

Range Verification and Dose Evaluation in Proton Therapy by Using Monte Carlo Method

, M.Sc. Thesis Sharif University of Technology Rabiee, Zahra (Author) ; Vosoughi, Naser (Supervisor)

Abstract

In this study, the emission and detection of secondary particles such as gamma and neutron along the beam path was investigated to evaluate proton range during treatment. Simulations and detections were performed by Geant4 toolkit that was developed base on Monte Carlo method. First, a mono-energetic proton beams irradiated a homogeneous water phantom. Then the factors influencing the accuracy of beam range estimation have been investigated and finally proton beam range was evaluated by simulation the human eye phantom. According to the results, the accuracy of range verification by prompt gamma is very high, about 1 mm. In phantoms with more oxygen in their composition, the percentage of...

A 3-D and Time Dependent Software for Particles Tracking Base on Monte Carlo Method

, Ph.D. Dissertation Sharif University of Technology Ghaderi Mazaher, Meysam (Author) ; Salehi, Ali Akbar (Supervisor) ; Vosoughi, Naser (Co-Supervisor)

Abstract

A highly reliable tool for transient simulation is vital in the safety analysis of a nuclear reactor. Despite this fact most tools still use diffusion theory and point-kinetics that involve many approximations such as discretization in space, energy, angle and time. However, Monte Carlo method inherently overcomes these restrictions and provides an appropriate foundation to accurately calculate the parameters of a reactor. For this reason, in this thesis, a dynamic Monte Carlo code named MCSP (Monte Carlo dynamic Simulation of Particles tracking) is developed for both the steady state and time-dependent simulation of particle (neutrons, photons and electrons) tracking in an arbitrary 3D...