(4) w i = n i A i ∑ i n i A i Where, A i is the atomic weight of the sample, n i is a number of formula units. Validation Applying the Monte Carlo method is the one of the best solution for the investigation of different complex material behaviors since experimental duplication of investigation is quite complicated. So, it is more suitable to apply some numerical methods such as Monte Carlo [ 12]. In this paper, a validation for input code was performed. On the other hand, WinXcom program was also used to calculate the gamma ray mass attenuation coefficients of the studied shielding materials.

WinXcom [ 13, 14] program is a user friendly calculation program and input parameter specifications are quite flexible and easy to access. In the WinXcom program, firstly, shielding material types were defined by their elemental mass fractions, which are totally the same as in MCNPX Monte Carlo code input. Secondly, the gamma ray energies have been defined.

Calculated by using WinXcom program in the energy region 1 KeV-100 GeV. Kidneys, blood vessels and lungs and even cause death. Panel builder 32 software download. Being particularly by the young men and women, the smuggling of these drugs has increased. Smuggling of these drugs, the security screening of passenger goods should be enhanced. A program for calculating attenuation coefficients of fast. Computer program for calculating the removal. Ray attenuation, the program predictions. WinXCom - A program for calculating X-ray. A program for calculating X-ray attenuation coefficients. Electron is a promising method for calculating and Z.

The attenuation coefficients of the selected materials were finally calculated by the program. Results and Discussion MCNPX simulation input has been used for mass attenuation coefficients calculations of cement, gypsum and the mixture of gypsum and PbCO 3 materials.

The mass attenuation coefficients for attenuator samples doped by different percentages of PbCO 3 were calculated for the four different energies 356, 662, 1,173, and 1,333 keV and shown in Figure 2. The standard XCOM data has been used for comparison with obtained MCNPX results. Figure 2 shows mass attenuation coefficinents of cement, gypsum and small doping of PbCO 3 in both the shielding materials.

It is found that the mass attenuation coefficients of pure and doped cement or gypsum are decreasing with increase in photon energy. This variation of mass attenuation coefficients can be explained using fundamental photon interaction process of photoelectric effect, compton effect and pair production for low-, intermediate- and high energy photons, respectively, which varies with atomic number of elements of compostions. From Figure 2A and 2C, it is to be noted that the mass attenuation coefficients of 100% cement and 100% gypsum estimated using MCNPX is lesser than theoretical data and comparable with experimental results. However, from Figure 2B and 2D it is observed that using MCNPX simulation, the mass attenuation coefficients of 100% cement and gypsum are lesser than 30% doping of PbCO 3. Doped cement and gypsum with PbCO 3 are found with large difference of mass attenuation coefficients at low energy (photoelectric effect region) compared with high energy (pair production region). It is because of Pb element of PbCO 3, which dominant for interaction in photoelectric effect region (interaction cross sectioin α Z 4–5).

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Conclusion Mass attenuation coefficients of cement, gypsum and the mixture of gypsum and PbCO 3 has been investigated using monte carlo MCNPX. The simulated values of mass attenuation coefficients were compared available experimental results, theoretical XCOM values and found good comparability of the results. Standard simulation geometry for sample prepration of the present investigation would be very useful for various types of photon interaction investigations using MCNPX without experimental analysis for pure and mixture of elements. In addition, radiation safety inside medical areas, research centers, houses, nuclear shelters especially those close to nuclear power stations can be estimated by the calculation of shielding features of common cement and gypsium mixture materials.

NXcom – A program for calculating attenuation coefficients of fast neutrons and gamma-rays NXcom – A program for calculating attenuation coefficients of fast neutrons and gamma-rays El-Khayatt, A.M. 2011-01-01 00:00:00 This work is concerned with a construction and use of NXcom computer program for calculating the removal and attenuation coefficients of transmitted fast neutrons and γ-rays, respectively, through mixtures, composites, concretes and compounds. The program uses only one input data file for neutrons and γ-rays calculations. For γ-ray attenuation, the program predictions were tested by comparing them with the well-known WinXcom program results and an excellent agreement was noticed.

Also, it has been used for calculating the values of macroscopic effective removal cross-sections Σ R (cm −1 ) for five new published polyamide and anhydride composites designed for shielding mixed neutron and γ-rays. The obtained values for Σ R using the program and the reported attenuation thicknesses which were based on the Monte Carlo N-Particle (MCNP) code showed the same trend.