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Use of MCNP code in energy dispersive X-ray fluorescence

Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 2007
Monte Carlo simulations enable us to improve the applicability of analytical techniques based on emission of characteristic radiation. In particular, the MCNP4C2 code was tested for interpretation of measured data obtained with the use of energy dispersive X-ray fluorescence analysis. This paper describes MCNP outputs and compares them with the results
T. Trojek, T. Čechák
openaire   +1 more source

Heart simulation with surface equations for using on MCNP code

AIP Conference Proceedings, 2011
External photon beam radiotherapy is carried out in a way to achieve an “as low as possible” a dose in healthy tissues surrounding the target. One of these surroundings can be heart as a vital organ of body. As it is impossible to directly determine the absorbed dose by heart, using phantoms is one way to acquire information around it. The other way is
D. Rezaei-Ochbelagh   +7 more
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Monte Carlo simulation of prompt gamma neutron activation analysis using MCNP code

Applied Radiation and Isotopes, 1998
Prompt gamma neutron activation analysis (PGNAA) is the most direct method of measuring total-body nitrogen. In combination with internal hydrogen standardisation, it is possible to reduce the dependence on body habitus. The uniformity of activation and detection, however, cannot be optimised sufficiently to eliminate the dependence entirely, and so ...
C J, Evans   +3 more
openaire   +2 more sources

Calculation of conversion coefficients for clinical photon spectra using the MCNP code

Radiation Protection Dosimetry, 2004
In this work, the MCNP4B code has been employed to calculate conversion coefficients from air kerma to the ambient dose equivalent, H*(10)/Ka, for monoenergetic photon energies from 10 keV to 50 MeV, assuming the kerma approximation. Also estimated are the H*(10)/Ka for photon beams produced by linear accelerators, such as Clinac-4 and Clinac-2500 ...
M A F, Lima, A X, Silva, V R, Crispim
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The Monte Carlo codes MCNP and MCU for RBMK criticality calculations

Nuclear Engineering and Design, 1998
Abstract The modern Monte Carlo codes MCNP and MCU have been established as important tools to determine the neutronic behavior of reactor cores. For a comparison of their capabilities, detailed representations of seven critical experiments performed at the Russian Research Center ‘Kurchatov Institute’ were developed, identical in geometry and ...
N Alexeev   +7 more
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Input File of Mathematical Phantom for MCNP-4B Code

2022
D. Krstić, D. Nikezić, N. Stevanović
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MONTE CARLO SIMULATION METHOD AND MCNP CODE SYSTEM

The Method of Monte Carlo is a system which is based upon the theory of possibility. What is fundamental in this method is to clarify a physics incident or experiment which has to be explained with statistical and mathematical techniques by using random numbers constantly in order to simulate.
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Application of the MCNP 5 code to simulate the shielding features of concrete samples with different aggregates

Radiation Physics and Chemistry, 2020
M I Sayyed   +2 more
exaly  

Gamma ray exposure buildup factor and shielding features for some binary alloys using MCNP-5 simulation code

Nuclear Engineering and Technology, 2021
Yasser Rammah   +2 more
exaly  

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