شیرانی, احمد
دانشگاه صنعتی اصفهان
[ 1 ] - محاسبات مصرف سوخت و پارامترهای نوترونیک مربوط به رآکتورهای آب سنگین تحقیقاتی با سوخت اورانیوم- توریوم توسط کد MCNPX
One of the main characteristics of heavy water research reactors is their high production of plutonium. This work demonstrates the possibility of reduction of plutonium production and other actinides in heavy water research reactors. Among the many ways for reducing plutonium production in a heavy water reactor, in this research, changing the fuel from natural uranium to thorium-uranium mixed f...
[ 2 ] - شبیه‌سازی مونت کارلو یک دستگاه پرتودهی نوترونی به منظور تعیین بازده آشکارسازهای نوترون‌های حرارتی
In this work, a neutron irradiating system containing six Am/Be neutron sources in a graphite moderator, which produces a relatively high and uniform thermal neutron flux in an irradiating cavity at the center of the system , has been simulated .The thermal neutron flux in the center of the system has then been calculated and compared with experimental results measured in a cavity a...
[ 3 ] - بررسی تغییرات راکتیویته راکتور MNSR اصفهان در اثر تغییر ضخامت لایه برلیوم سقف قلب راکتور با استفاده از کدهای محاسباتی WIMSD و MCNP و مقایسه با نتایج تجربی
In this work, the Isfahan Miniature Neutron Source Reactor (MNSR) is first simulated using the WIMSD code, and its fuel burn-up after 7 years of operation ( when the reactor was revived by adding a 1.5 mm thick beryllium shim plate to the top of its core) and also after 14 years of operation (total operation time of the reactor) is calculated. The reactor is then simulated using the MCNP code,...
[ 4 ] - Efficiency determination of HPGe detector by simulation and experimental methods for solid volume source
Analyzes of environmental samples regarding their radioactivity is of important concern for health purposes. We need standard sources to determine radioactive components and their activities. These sources are usually produced regarding type of the sample. One of the fundamental and precise tools to recognize radioactive materials and their activities is HPGe detector. To reach this goal, the d...
[ 5 ] - Determination of virtual point for HPGe detector at various gamma rays energies by simulation and experimental methods
High Purity Germanium detectors (HPGe) are subdivisions of semiconductor detectors which are widely used in nuclear technology from space industry to nuclear medicine, due to their high resolution, low dead time, unlimited size and compatibility with a variety of environments. The( absolute and intrinsic) efficiency of the HPGe detector, which depends on the geometry of the source-detector syst...
[ 6 ] - Absorbed dose of Fetus in SPECT-CT Imaging of Mother's Abdomen Regions using Monte Carlo method
SPECT-CT is an imaging method for diagnosing diseases and studying physiology of the body. In this type of imaging, due to the use of radiopharmaceutical for imaging (SPECT) and X-rays (CT), a relatively high dose of radiation is introduced into the patient. If the patient is pregnant, considering that the developing fetus is sensitive to any radiation in the uterus throughout the entire period...