Zobrazeno 1 - 10
of 218
pro vyhledávání: '"T. El Bardouni"'
Autor:
M. Makhloul, H. Boukhal, E. Chakir, T. El Bardouni, M. Lahdour, M. Kaddour, Abdulaziz Ahmed, A. Arectout, H. El Yaakoubi
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 2, Pp 523-531 (2022)
In order to study the sensitivity and the uncertainty of the Moroccan research reactor TRIGA Mark II, a model of this reactor has been developed in our ERSN laboratory for use with the N-Particle MCNP Monte Carlo transport codes (version 6). In this
Externí odkaz:
https://doaj.org/article/7cdde4224e7d458c996e77ab1224e346
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 4, Pp 1079-1087 (2021)
NTP-ERSN is a package developed for solving the multigroup form of the discrete ordinates, characteristics and collision probability of the Boltzmann transport equation in one-dimensional cartesian geometry, by combining pin cells. In this work, C5G7
Externí odkaz:
https://doaj.org/article/63901bfb287144fabe739fed140a81a3
Publikováno v:
Nuclear Engineering and Technology, Vol 52, Iss 6, Pp 1120-1130 (2020)
The CREOLE experiment performed In the EOLE critical facility located In the Nuclear Center of CADARACHE - CEA have allowed us to get interesting and complete experimental information on the temperature effects in the light water reactor lattices.To
Externí odkaz:
https://doaj.org/article/27ae6b4797494f898b083da57c7eebd6
Publikováno v:
Journal of King Saud University: Science, Vol 32, Iss 1, Pp 288-293 (2020)
This study is aimed to calculate the conversion coefficients H∗(10)/Φ form air-kerma for beams of mono-energetic photons, which incident on ICRU sphere diameter 30 cm of ICRU tissues material with a density of 1 g/cm3 four-element tissue and a wei
Externí odkaz:
https://doaj.org/article/dee2827ab48d4fa3a2d9cec237422790
Publikováno v:
Journal of King Saud University: Science, Vol 30, Iss 4, Pp 537-543 (2018)
Accurate dose calculation in the treatment planning system (TPS) process is the most important step to succeed the radiation therapy. For this purpose, Monte Carlo method is a powerful tool for dose calculation. This study aims to validate Monte Carl
Externí odkaz:
https://doaj.org/article/7ce2bdf4f3bc4818ab712c01540a415a
Publikováno v:
Journal of Radiation Research and Applied Sciences, Vol 11, Iss 3, Pp 255-261 (2018)
Comparative studies for conversion of the fuel from high enriched uranium (HEU) to low enriched uranium (LEU) in the reactor (MNSR) were performed using DRAGON code deterministic. In this work the HEU fuel (UAl4-Al, 90% enriched with Al-clad) and LEU
Externí odkaz:
https://doaj.org/article/920b164aad5241a7977a446770b60439
Publikováno v:
Results in Physics, Vol 9, Iss , Pp 1155-1160 (2018)
The MNSR is a pool type research reactor, which is difficult to model because of the importance of neutron leakage. The aim of this study is to evaluate a 2-D transport model for the reactor compatible with the latest release of the DRAGON code and 3
Externí odkaz:
https://doaj.org/article/9285e91d7b8f421ba99becfa0a46ff0e
Publikováno v:
Journal of King Saud University: Science, Vol 29, Iss 3, Pp 371-379 (2017)
This work aims to compare and evaluate the dosimetric properties of 6 MV flattening (FF) and flattening filter free (FFF) photon beams which generated from a Varian 2100 medical accelerator. These properties include percentage depth dose, dose rate,
Externí odkaz:
https://doaj.org/article/a83bdacd310443bdadc0cb20cc8320c8
Publikováno v:
Heliyon, Vol 5, Iss 8, Pp e02211- (2019)
In many deterministic methods, concerning the resolution of the neutron transport equation, a more global and practical representation of the angular flux is needed to provide us with useful and complete information on the neutron population in a rea
Externí odkaz:
https://doaj.org/article/38f83f08506c483a87753dde2c533cb5
Publikováno v:
Journal of Radiation Research and Applied Sciences, Vol 9, Iss 4, Pp 424-430 (2016)
The application of Variance Reduction Techniques (VRT) in Monte Carlo (MC) codes brings significant improvement in efficiency and a significant profit in the time of simulation. Monte Carlo radiation transport codes have provided by these techniques
Externí odkaz:
https://doaj.org/article/897fa530824b43dd9608ede19bd39aa1