نتایج جستجو برای: mcnpx code
تعداد نتایج: 168222 فیلتر نتایج به سال:
Introduction: The use of ionizing radiation in diagnostic medicine is expanding, and considering the fact that the practical dosimeter in a precise way is almost impossible, the Monte Carlo computational methods help researchers, to have coming up the lowest cost and error of the distribution of doses in the patient's body. Materials and Methods: In this st...
Objective: Different categories are available for estimating of radiation dose. Radioisotopes with the same energy and almost the same physical properties have similar effects. Monte Carlo technique is a computerized method based on mathematical simulation of physical processes. The main purpose of this study is to show that beta particles are not able to penetrate deep into the water. also dif...
In this study, the energy spectrum of beta-nickel 63 is considered as the total energy spectrum, average energy of the spectrum, and maximum spectral energy for analyzing the penetration depth of silicon. Monte Carlo calculations were carried out using a MCNPX code in a given geometry; in the following, Stopping-Power for electrons with different energies in silicon was calculated using the EST...
In this research, required information to simulate and perform neutronic calculations for Bushehr nuclear power plant using the MCNPX code was provided. The results of the code were verified with at least one of the operational data from the reactor. In this work, by writing and implementing a comprehensive program to solve the equations of statistical distribution, neutron flux was obtained an...
In this article, a criticality and depletion analysis of the European Lead-Cooled Training Reactor (ELECTRA), low-power, compact, fast lead-cooled reactor, was performed. The active core model simulations were made by using MCNPX code. First, is compared with reference influence reflector radius on system analyzed. Secondly, it simulated fuel combustion after 30 years continuous operation ELECT...
This work illustrates a methodology based on photon interrogation and coincidence counting for determining the characteristics of fissile material. The feasibility of the proposed methods was demonstrated using the Monte Carlo-based MCNPX/MCNPPoliMi code system capable of simulating the full statistics of the neutron and photon field generated by the photon interrogation of fissile and non-fiss...
Objective: Different categories are available for estimating of radiation dose. Radioisotopes with the same energy and almost the same physical properties have similar effects. Monte Carlo technique is a computerized method based on mathematical simulation of physical processes. The main purpose of this study is to show that beta particles are not able to penetrate deep into the water. also dif...
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