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Low-energy neutron flux measurement using a resonance absorption filter surrounding a lithium glass scintillator
filter surrounding a miniature-type lithium glass scintillator. the count with and without the filter surrounding the detector gives the number of resonance-energy neutrons. Some preliminary results and a comparison with the MCNP code are shown....
دز سنجی پرتوهای مصنوعی در محیط زیست با استفاده از کد MCNP
Nuclear disaster spread radioisotopes greatly to the environment. The isotopes fall on the surface earth, radiate and pollute the environment. So dosimetric data for estimating the accident is necessary. For this reason, ...
Calculation of neutron self-shielding factor and its effect on estimating amount of sample matter in LS-PGNAA
factor is calculated and its effect on correction of full energy peak in prompt gamma spectrum is investigated. For calculating this factor a simulation was carried out using MCNP code. samples put in cylindrical PTFE (poly tetra fluor ethylene) container...
The investigation of Am - Be neutron source shield effect used on landmine detection
In this work, experiments were carried out to investigate the possible use of neutron backscattering for the detection of sample buried in the soil. A series of Monte Carlo simulations were performed to study the complexity ...
Momte Carlo simulation of pulse pile-up effect in gamma spectrum of a PGNAA system
We have applied a pile-up Monte Carlo simulation code on gamma spectrum of a prompt gamma
neutron activation analysis (PGNAA) system. The code has been run in nonparalyzable mode for a
specific geometry of a ...
Calibration Constant of a Silver Activated Geiger Counter Used for Neutron Efficiency Measurements in Plasma Focus Devices: Theoretical vs. Experimental Studies
The silver activated Geiger counters are frequently used for measuring pulsed neutron fluxes especially in plasma focus devices. These counters basically utilize a Geiger-Mueller (GM) counter surrounded by a silver layer ...
The effect of source shield on landmine detection
neutron
backscattering are nuclear-based methods used for
landmine detection. The aim of this study is to use
backscattered neutron for landmine detection.
Materials and Methods: MCNP code, a well-known
Monte Carlo...
Optimization of a Detector Collimator for Use in a Gamma-Ray Backscattering Device for Anti-Personal Landmines Detection
In the present study, a new detector collimator has been designed to detect the buried anti-personal (AP) landmines for use in gamma-ray backscattering device, with Monte Carlo method. The new detector collimator is made ...
Activation rate uniformity in a bilateral IVNAA facility for two anthropomorphic phantoms
Activation rate uniformity is the first property which is considered in the design of a prompt g -ray in vivo neutron activation analysis facility. Preliminary studies on the activation rate distribution in the body can ...
Monte Carlo Calculation of Relative Dose Distribution and Dosimetry Parameters for an 192Ir Source in a Water Phantom Using MCNP4C
The dose distribution has been calculated around a high dose rate
192Ir source located in the center of 30 cm ×30 cm ×30 cm water
phantom cube using MCNP code by Monte Carlo method. The
percentage depth dose (PDD) variation...